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  <doc>
    <id>30378</id>
    <completedYear/>
    <publishedYear>2013</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>55</pageFirst>
    <pageLast>59</pageLast>
    <pageNumber/>
    <edition/>
    <issue>2</issue>
    <volume>24</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Approach for use of acceleration values for packages of radioactive material under routine conditions of transport</title>
    <abstract language="eng">The most relevant source of reference for load cases of packages for the transport of radioactive material under routine conditions is Appendix IV of the International Atomic Energy Agency (IAEA) Advisory Material TS-G-1·1. The acceleration values given there leave many questions open and have to be agreed upon with the involved competent authorities. Consequently, the actual load cases applied for a safety analysis may differ widely and could cause problems for international transport. To avoid such difficulties, it seems obvious that the according passages in TS-G-1·1 should be modified with the objective of making the load case data more consistent for a harmonized application in the IAEA member states. Papers pointing out in this direction were discussed at the PATRAM 2010 conference. The way to improve the acceleration data may lie in investigations and measurements considering, for example different types of vehicles and package masses. However, what should be the goal of such kind of surveys? Can such investigation provide values for every worldwide load case possible under routine conditions of transport? In particular, the different designs of vehicles give a reason to doubt that such an aim is realistic. The approach in this paper is to show that a less ambitious aim is more effective. Therefore, an approximate scheme is preferred, which renders better assistance in determining the appropriate acceleration values.</abstract>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">33348</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <author>Andreas Apel</author>
    <author>Viktor Ballheimer</author>
    <author>Christian Kuschke</author>
    <author>Sven Schubert</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive materials</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety assessment</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>IAEA regulations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Load cases</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Routine conditions of transport</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>IAEA advisory material TS-G-1.1</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Appendix IV</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Revision of load case data</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Acceleration values</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
  </doc>
  <doc>
    <id>58577</id>
    <completedYear/>
    <publishedYear>2023</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst>16</pageFirst>
    <pageLast>18</pageLast>
    <pageNumber/>
    <edition/>
    <issue>9</issue>
    <volume>2023</volume>
    <type>article</type>
    <publisherName>Heinrich Vogel</publisherName>
    <publisherPlace>München</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Neue Regel für das Alterungsmanagement</title>
    <abstract language="deu">Die Regelwerksanforderungen für Verpackungen für den Transport radioaktiver Stoffe basieren auf den Empfehlungen der IAEA und werden über die verkehrsträgerspezifischen internationalen Regelwerke in nationales Recht umgesetzt.&#13;
Um die Anforderungen des Regelwerkes zu erläutern, entwickelt die Bundesanstalt für Materialforschung und -prüfung (BAM) Gefahrgutregeln (BAM-GGR), welche die Entwickler, Hersteller und Betreiber von Behältern über die von der BAM angewandten Verfahren bei der Umsetzung gesetzlicher Bestimmungen informieren und unterstützen sollen.</abstract>
    <parentTitle language="deu">Gefahrgut</parentTitle>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="opus.doi.autoCreate">false</enrichment>
    <enrichment key="opus.urn.autoCreate">true</enrichment>
    <author>Steffen Komann</author>
    <author>Frank Wille</author>
    <author>Sven Schubert</author>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Gefahrgut</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Radioaktive Stoffe</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Alterung</value>
    </subject>
    <subject>
      <language>deu</language>
      <type>uncontrolled</type>
      <value>Transport</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>32193</id>
    <completedYear/>
    <publishedYear>2010</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8(?)</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation>PATRAM</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Verification of activity release compliance with regulatory limits within spent fuel transport casks</title>
    <parentTitle language="eng">PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials (Proceedings)</parentTitle>
    <identifier type="old">35258</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="eventName">PATRAM 2010 - 16th International symposium on the packaging and transport of radioactive materials</enrichment>
    <enrichment key="eventPlace">London, UK</enrichment>
    <enrichment key="eventStart">2010-10-03</enrichment>
    <enrichment key="eventEnd">2010-10-08</enrichment>
    <author>Annette Rolle</author>
    <author>Bernhard Droste</author>
    <author>Sven Schubert</author>
    <author>Ulrich Probst</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive material</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety assessment</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Leakage mechanism</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Leakage rate</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Sealing behavior</value>
    </subject>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>30264</id>
    <completedYear/>
    <publishedYear>2013</publishedYear>
    <thesisYearAccepted/>
    <language>deu</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="deu">Assessment Feedback on Material Compatability and Determination of Material Parameters for Transport Packages used as Dual Purpose Casks</title>
    <parentTitle language="deu">International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013)</parentTitle>
    <identifier type="old">33225</identifier>
    <enrichment key="eventName">International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2013)</enrichment>
    <enrichment key="eventPlace">San Francisco, CA, USA</enrichment>
    <enrichment key="eventStart">2013-08-18</enrichment>
    <enrichment key="eventEnd">2013-08-23</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Sven Schubert</author>
    <collection role="fulltextaccess" number="">Weder Datei noch physisches Exemplar vorhanden ("No Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>33428</id>
    <completedYear/>
    <publishedYear>2014</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>105</pageFirst>
    <pageLast>112</pageLast>
    <pageNumber/>
    <edition/>
    <issue>3-4</issue>
    <volume>25</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW</title>
    <abstract language="eng">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'.</abstract>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">36522</identifier>
    <identifier type="doi">10.1179/1746510914Y.0000000070</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <author>Bernhard Droste</author>
    <author>Steffen Komann</author>
    <author>Frank Wille</author>
    <author>Annette Rolle</author>
    <author>Ulrich Probst</author>
    <author>Sven Schubert</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent fuel</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>High-level waste</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Aging</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Metal seals</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport and storage casks</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Spent nuclear fuel</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Aging mechanisms</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Corrosion</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety assessment</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
  </doc>
  <doc>
    <id>18624</id>
    <completedYear/>
    <publishedYear>2007</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>Institute of Nuclear Materials Management</publisherName>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Comparison of experimental results from drop testing of a spent fuel package design using a full-scale prototype model and a reduced-scale model</title>
    <parentTitle language="eng">PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings)</parentTitle>
    <identifier type="old">20783</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="eventName">PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials</enrichment>
    <enrichment key="eventPlace">Miami, Florida, USA</enrichment>
    <enrichment key="eventStart">2007-10-21</enrichment>
    <enrichment key="eventEnd">2007-10-26</enrichment>
    <author>Thomas Quercetti</author>
    <author>Karsten Müller</author>
    <author>Sven Schubert</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Drop</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Testing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Experiment</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Prototype</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Reduced-scale</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Full-scale</value>
    </subject>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>20135</id>
    <completedYear/>
    <publishedYear>2008</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>197</pageFirst>
    <pageLast>202</pageLast>
    <pageNumber/>
    <edition/>
    <issue>4</issue>
    <volume>19</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Comparison of experimental results from drop testing of spent fuel package design using full scale prototype model and reduced scale model</title>
    <abstract language="eng">This paper presents a comparison between full scale prototype and reduced scale model drop test data in regard to similarity mechanics. Together with a current BAM research project, the paper contributes to the further development of mechanical evaluation methods for safety assessment of RAM transport and storage packages including the transferability of package impact response from reduced scale models to full scale packages.</abstract>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">22418</identifier>
    <identifier type="doi">10.1179/174651008X362575</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <author>Thomas Quercetti</author>
    <author>Karsten Müller</author>
    <author>Sven Schubert</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Full scale</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Reduced scale</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Drop testing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Similarity</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
  </doc>
  <doc>
    <id>20708</id>
    <completedYear/>
    <publishedYear>2009</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>179</pageFirst>
    <pageLast>182</pageLast>
    <pageNumber/>
    <edition/>
    <issue>4</issue>
    <volume>20</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Behaviour of metallic seals in CASTOR casks under normal and accident conditions of transport: qualification requirements</title>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">23024</identifier>
    <identifier type="doi">10.1179/174651009X12555104004055</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <author>Sven Schubert</author>
    <author>Ulrich Probst</author>
    <author>H. P. Winkler</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport cask</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Seal</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Leak tightness</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Accident</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Qualification program</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transportbehälter</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioaktive Stoffe</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Dichtung</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Dichtheit</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Unfall</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Qualifikationsprogramm</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
  </doc>
  <doc>
    <id>12035</id>
    <completedYear/>
    <publishedYear>1999</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst>37</pageFirst>
    <pageLast>41</pageLast>
    <pageNumber/>
    <edition/>
    <issue>4</issue>
    <volume>40</volume>
    <type>article</type>
    <publisherName>Springer-VDI-Verl.</publisherName>
    <publisherPlace>Düsseldorf</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Verhalten von metallenen Großpackmitteln (IBC) und ihrer Druckausgleichseinrichtungen unter äußerer Feuereinwirkung</title>
    <parentTitle language="deu">Technische Überwachung</parentTitle>
    <identifier type="old">13737</identifier>
    <identifier type="issn">1434-9728</identifier>
    <identifier type="issn">1436-4948</identifier>
    <identifier type="issn">0372-2457</identifier>
    <identifier type="issn">0376-1185</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="bibliotheksstandort">ZT 7</enrichment>
    <author>Sven Schubert</author>
    <author>Werner Kraus</author>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
  </doc>
  <doc>
    <id>16143</id>
    <completedYear/>
    <publishedYear>2007</publishedYear>
    <thesisYearAccepted/>
    <language>deu</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="deu">Behaviour of metallic seals in CASTOR-casks under normal and accident conditions of transport: qualification requirements</title>
    <parentTitle language="deu">PATRAM 2007, The 15th International Symposium on the Packaging and Transportation of Radioactive Materials</parentTitle>
    <identifier type="old">18105</identifier>
    <enrichment key="eventName">PATRAM 2007, The 15th International Symposium on the Packaging and Transportation of Radioactive Materials</enrichment>
    <enrichment key="eventPlace">Miami, FL, USA</enrichment>
    <enrichment key="eventStart">2007-10-22</enrichment>
    <enrichment key="eventEnd">2007-10-26</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Sven Schubert</author>
    <collection role="fulltextaccess" number="">Weder Datei noch physisches Exemplar vorhanden ("No Access")</collection>
    <collection role="literaturgattung" number="">Präsentation</collection>
  </doc>
  <doc>
    <id>16105</id>
    <completedYear/>
    <publishedYear>2007</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>Institute of Nuclear Materials Management</publisherName>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">State-of-the-art assessment of package design safety analyses</title>
    <parentTitle language="eng">PATRAM 2007 - 15th International symposium on the packaging and transportation of radioactive materials (Proceedings)</parentTitle>
    <identifier type="old">18066</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="eventName">PATRAM 2007, 15th International Symposium on the Packaging and Transportation of Radioactive Materials</enrichment>
    <enrichment key="eventPlace">Miami, Florida, USA</enrichment>
    <enrichment key="eventStart">2007-10-21</enrichment>
    <enrichment key="eventEnd">2007-10-26</enrichment>
    <author>Frank Wille</author>
    <author>Bernhard Droste</author>
    <author>Frank Koch</author>
    <author>Sven Schubert</author>
    <author>Steffen Komann</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transportation of radioactive materials</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Design assessment</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Mechanical tests</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Thermal tests</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Drop tests</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Numerical calculations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Quality assurance</value>
    </subject>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>26241</id>
    <completedYear/>
    <publishedYear>2012</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>11</pageLast>
    <pageNumber/>
    <edition/>
    <issue>4.4 RAM 30</issue>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation>Nuclear institute (ni)</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Moisture content of wood - influence on mechanical behavior of wood filled impact limiter and importance for quality surveillance during manufacturing</title>
    <abstract language="eng">The moisture content of wood is known to have a significant influence on the woods mechanical properties. Using wood as an energy absorber in impact limiter of packages for the transport of radioactive material, it is of particu-lar importance to ensure the moisture content and thus relevant mechanical properties to be in specified limits. The paper surveys the influence of wood moisture content on the mechanical properties of wood. Different measuring methods are discussed with respect to in-situ applicability, accuracy and effort. The results of an experimental ana-lysis of the accuracy of hand-held moisture meters using the electrical resistance method are discussed. Conclu-sions are drawn regarding the measurement of moisture content of wood upon delivery as well as of complete im-pact limiter assemblies. Requirements for quality surveillance during manufacturing of wood filled impact limiter are derived and it is exemplified how to meet them. Construction, manufacturing and inspection of impact limiter encapsulation with regard to leak-tightness are addressed.</abstract>
    <parentTitle language="eng">RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage (Proceedings)</parentTitle>
    <identifier type="old">28991</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="eventName">RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage</enrichment>
    <enrichment key="eventPlace">London, UK</enrichment>
    <enrichment key="eventStart">2012-05-22</enrichment>
    <enrichment key="eventEnd">2012-05-24</enrichment>
    <author>Germar Eisenacher</author>
    <author>Christian Kuschke</author>
    <author>Sven Schubert</author>
    <author>Martin Neumann</author>
    <author>Jens Sterthaus</author>
    <author>Thilo Nitz</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Mechanical behavior of wood</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Moisture content</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Impact limiter</value>
    </subject>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>26747</id>
    <completedYear/>
    <publishedYear>2012</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation>Nuclear institute (ni)</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Approach for the use of acceleration values for packages of radioactive material under routine conditions of transport</title>
    <abstract language="deu">The most relevant source of reference for load cases of packages for the transport of radioactive material under routine conditions is Appendix IV of the International Atomic Energy Agency (IAEA) Advisory Material TS-G-1·1. The acceleration values given there leave many questions open and have to be agreed upon with the involved competent authorities. Consequently, the actual load cases applied for a safety analysis may differ widely and could cause problems for international transport. To avoid such difficulties, it seems obvious that the according passages in TS-G-1·1 should be modified with the objective of making the load case data more consistent for a harmonized application in the IAEA member states. Papers pointing out in this direction were discussed at the PATRAM 2010 conference. The way to improve the acceleration data may lie in investigations and measurements considering, for example different types of vehicles and package masses. However, what should be the goal of such kind of surveys? Can such investigation provide values for every worldwide load case possible under routine conditions of transport? In particular, the different designs of vehicles give a reason to doubt that such an aim is realistic. The approach in this paper is to show that a less ambitious aim is more effective. Therefore, an approximate scheme is preferred, which renders better assistance in determining the appropriate acceleration values.</abstract>
    <parentTitle language="eng">RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage (Proceedings)</parentTitle>
    <identifier type="old">29529</identifier>
    <enrichment key="eventName">RAMTRANSPORT 2012 - 9th International Conference on the Radioactive Materials Transport and Storage</enrichment>
    <enrichment key="eventPlace">London, UK</enrichment>
    <enrichment key="eventStart">22.05.2012</enrichment>
    <enrichment key="eventEnd">24.05.2012</enrichment>
    <author>Andreas Apel</author>
    <author>Viktor Ballheimer</author>
    <author>Christian Kuschke</author>
    <author>Sven Schubert</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive materials</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Safety assessment</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>IAEA regulations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Lost cases</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Routine conditions of transport</value>
    </subject>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>1118</id>
    <completedYear/>
    <publishedYear>2001</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst>107</pageFirst>
    <pageLast>112</pageLast>
    <pageNumber/>
    <edition/>
    <issue>1599</issue>
    <volume/>
    <type>bookpartcollection</type>
    <publisherName>VDI-Verl.</publisherName>
    <publisherPlace>Düsseldorf</publisherPlace>
    <creatingCorporation>Gesellschaft Mess- und Automatisierungstechnik / Gemeinschaft Experimentelle Strukturanalyse</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Berechnung, Simulation und Messung von Transportbeschleunigungen im Seeverkehr</title>
    <parentTitle language="deu">Sicherheit und Zuverlässigkeit durch experimentelle Struktur- und Beanspruchungsanalyse</parentTitle>
    <identifier type="old">637</identifier>
    <identifier type="isbn">3-18-091599-4</identifier>
    <identifier type="issn">0083-5560</identifier>
    <note>Serientitel: VDI-Berichte – Series title: VDI-Berichte</note>
    <author>Norbert Mayer</author>
    <author>Michael Kammermeier</author>
    <author>Sven Schubert</author>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Weder Datei noch physisches Exemplar vorhanden ("No Access")</collection>
  </doc>
  <doc>
    <id>1881</id>
    <completedYear/>
    <publishedYear>2002</publishedYear>
    <thesisYearAccepted/>
    <language>deu</language>
    <pageFirst>27</pageFirst>
    <pageLast>29</pageLast>
    <pageNumber/>
    <edition/>
    <issue>5</issue>
    <volume>45</volume>
    <type>article</type>
    <publisherName>Storck</publisherName>
    <publisherPlace>Hamburg</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="deu">Rolling home</title>
    <parentTitle language="deu">Gefährliche Ladung</parentTitle>
    <identifier type="old">1759</identifier>
    <identifier type="issn">0016-5808</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <enrichment key="bibliotheksstandort">ZG 4</enrichment>
    <author>Thomas Goedecke</author>
    <author>Sven Schubert</author>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
  </doc>
  <doc>
    <id>57770</id>
    <completedYear/>
    <publishedYear>2023</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>10</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>World Nuclear Transport Institute (WNTI)</publisherName>
    <publisherPlace>London</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Introduction of the German ageing management guide for packages for transport of radioactive materials</title>
    <abstract language="eng">The consideration of ageing mechanisms is with integration of the new para 613A into IAEA SSR-6 (Rev. 1) now obligatory for the design of transport packages. In addition, para 809(f) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that all packaging components and radioactive contents have been maintained during storage in a manner that all requirements specified in IAEA SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled.&#13;
&#13;
The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled a guideline for the implementation of ageing assessment and of the measures for ageing management of the approval procedure based on requirements of IAEA SSR-6 (Rev.1). The guideline is applicable only for packages requiring a competent authority approval.&#13;
&#13;
The paper aims to describe the structure of the guideline and the general approach for ageing management requirements. The type and amount of measures for ageing management depend mainly on the use of the package and on the ageing effects for the component, which result from relevant ageing mechanisms during package operation time.&#13;
&#13;
The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan (AMP). These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program (ASP) and, if necessary, a gap analysis program shall be developed. The ageing management documentation (AMD) ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance.</abstract>
    <parentTitle language="eng">Proceedings of the 20th international symposium on the packaging and transportation of radioactive materials</parentTitle>
    <enrichment key="eventName">PATRAM22 - 20th International Symposium on the Packaging and Transportation of Radioactive Materials</enrichment>
    <enrichment key="eventPlace">Juan-les-Pins, France</enrichment>
    <enrichment key="eventStart">11.06.2023</enrichment>
    <enrichment key="eventEnd">15.06.2023</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <author>Sven Schubert</author>
    <author>Adrian Reichardt</author>
    <author>Lars Müller</author>
    <author>Martin Neumann</author>
    <author>Steffen Komann</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Guide</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Mechanism</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Package</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Management</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
    <collection role="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>57821</id>
    <completedYear/>
    <publishedYear>2023</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">Introduction of the German Ageing Management Guide for Packages for Transport of Radioactive Materials –  BAM-GGR 023</title>
    <abstract language="eng">BAM-GGR 023 was published in June 2022 &#13;
&#13;
BAM-GGR 023 gives guidance to applicants regarding ageing management for competent authority approved package designs&#13;
&#13;
Ageing management with evaluation of ageing mechanisms according to para 613A of IAEA SSR-6 (Rev. 1) and their effects are part of the general management system.&#13;
&#13;
Essential items are: AMS (systemic-related), AMP (package design-related) and AMD (package-related)&#13;
&#13;
There are different requirements for organization and extent of ageing management depending on type of use&#13;
&#13;
There are also different requirements for ageing evaluation depending on type of use for packaging/package, classification of components and their accessibility and replaceability</abstract>
    <enrichment key="eventName">PATRAM22</enrichment>
    <enrichment key="eventPlace">Juan-les-Pins, France</enrichment>
    <enrichment key="eventStart">11.06.2023</enrichment>
    <enrichment key="eventEnd">15.06.2023</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="opus.doi.autoCreate">false</enrichment>
    <enrichment key="opus.urn.autoCreate">true</enrichment>
    <enrichment key="InvitedTalks">0</enrichment>
    <author>Sven Schubert</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Package</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Mechanism</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Management</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Guide</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</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="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>29243</id>
    <completedYear/>
    <publishedYear>2012</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>179</pageFirst>
    <pageLast>185</pageLast>
    <pageNumber/>
    <edition/>
    <issue>3-4</issue>
    <volume>23</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Moisture content of wood: influence on mechanical behaviour of wood filled impact limiters and importance for quality surveillance during manufacturing</title>
    <abstract language="eng">The moisture content of wood is known to have a significant influence on the wood's mechanical properties. Using wood as an energy absorber in impact limiters of packages for the transport of radioactive material, it is of particular importance to ensure the moisture content and thus relevant mechanical properties to be in specified limits. The paper surveys the influence of wood moisture content on the mechanical properties of wood. Different measuring methods are discussed with respect to in situ applicability, accuracy and effort. The results of an experimental analysis of the accuracy of hand held moisture metres using the electrical resistance method are discussed. Conclusions are drawn regarding the measurement of moisture content of wood upon delivery as well as of complete impact limiter assemblies. Requirements for quality surveillance during manufacturing of wood filled impact limiters are derived and it is exemplified how to meet them. Construction, manufacturing and inspection of impact limiter encapsulation with regard to leak tightness are addressed.</abstract>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">32151</identifier>
    <identifier type="doi">10.1179/1746510913Y.0000000023</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <enrichment key="bibliotheksstandort">Sonderstandort: Publica-Schrank</enrichment>
    <author>Germar Eisenacher</author>
    <author>Christian Kuschke</author>
    <author>Sven Schubert</author>
    <author>Martin Neumann</author>
    <author>Jens Sterthaus</author>
    <author>Thilo Nitz</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Electrical resistance method</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Impact limiter</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Moisture content</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Moisture metre</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Wood</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Physisches Exemplar in der Bibliothek der BAM vorhanden ("Hardcopy Access")</collection>
  </doc>
  <doc>
    <id>30270</id>
    <completedYear/>
    <publishedYear>2013</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>12</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>Omnipress</publisherName>
    <publisherPlace/>
    <creatingCorporation>Institute of Nuclear Materials Management (INMM)</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Reflection on BAM mechanical design assessment of TN®24E spent fuel transport package</title>
    <abstract language="eng">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.</abstract>
    <parentTitle language="eng">PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials (Proceedings)</parentTitle>
    <identifier type="old">33232</identifier>
    <enrichment key="eventName">PATRAM 2013 - 17th International symposium on the packaging and transportation of radioactive materials</enrichment>
    <enrichment key="eventPlace">San Francisco, CA, USA</enrichment>
    <enrichment key="eventStart">18.08.2013</enrichment>
    <enrichment key="eventEnd">23.08.2013</enrichment>
    <author>Martin Neumann</author>
    <author>Frank Wille</author>
    <author>Konrad Linnemann</author>
    <author>Sven Schubert</author>
    <author>Viktor Ballheimer</author>
    <author>Jens Sterthaus</author>
    <author>Bernhard Droste</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>RAM</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive material cask</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Nuclear fuel</value>
    </subject>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
  </doc>
  <doc>
    <id>53180</id>
    <completedYear/>
    <publishedYear>2021</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>6</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>Institute of Nuclear Materials Management (INMM)</publisherName>
    <publisherPlace>Mount Laurel, NJ</publisherPlace>
    <creatingCorporation>European Safeguards Research and Development Association (ESARDA)</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Introduction of an ageing management approach for packages for the transport of radioactive materials</title>
    <abstract language="eng">With integration of the new para 613A into SSR-6 [1] the consideration of ageing mechanisms is now obligatory for the design of packages and their approval. In addition, para 809(f) of SSR-6 [1] requires consideration of the effects of storage on ageing mechanisms, safety analyses and operation and maintenance instructions.&#13;
German competent authorities Bundesanstalt für Materialforschung und -prüfung (BAM) and Bundesamt für die Sicherheit der nuklearen Entsorgung (BASE) are considering the aspect of ageing in approval procedures. Ageing assessment is mainly focused on dual purpose casks (DPC) package designs which are long-term stored in interim storage facilities. For these package designs, the evaluation of ageing management is now mandatory for the maintenance of the package design approvals with a validity period of 5 years and beyond. The ageing management includes amongst others a gap analysis, the assessment of ageing effects and operational experiences during operation and interim storage.&#13;
BAM works on the compilation of a guideline for implementation of paras 613A, 809(f) and 809(k) for packages requiring competent authority approval at the application procedure in Germany. The paper describes essential items of ageing mechanisms and will give a foresight to the ageing management evaluation by BAM.</abstract>
    <parentTitle language="eng">Proceedings of the INMM &amp; ESARDA Joint Annual Meeting</parentTitle>
    <identifier type="url">https://www.abstractsonline.com/pp8/#!/10383/presentation/964</identifier>
    <enrichment key="eventName">INMM &amp; ESARDA Joint Annual Meeting</enrichment>
    <enrichment key="eventPlace">Online meeting</enrichment>
    <enrichment key="eventStart">30.08.2021</enrichment>
    <enrichment key="eventEnd">01.09.2021</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="RelatedIdentifier">https://opus4.kobv.de/opus4-bam/frontdoor/index/index/docId/53197</enrichment>
    <author>Sven Schubert</author>
    <author>Adrian Reichardt</author>
    <author>Frank Wille</author>
    <author>Steffen Komann</author>
    <author>Martin Neumann</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Dual purpose casks</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>SSR-6</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Interim storage</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing mechanisms</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport of radaioactive materials</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
    <collection role="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>63987</id>
    <completedYear/>
    <publishedYear>2025</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>INMM</publisherName>
    <publisherPlace>Washington D.C.</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Experiences with the implementation of ageing management for packages for transport of radioactive materials in Germany</title>
    <abstract language="eng">The consideration of ageing mechanisms is now obligatory for the design of transport packages with integration of the para 613A into IAEA SSR-6 (Rev. 1). In addition, para 809(f) of SSR-6 (Rev. 1) requires for packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance. Para 503(e) requires that these packages have been maintained during storage in a manner that all requirements specified in SSR-6 (Rev.1) and in the applicable certificates of approval have been fulfilled.&#13;
The evaluation of ageing mechanisms and their effects including monitoring are part of BAM’s authority assessment tasks related to the mechanical and thermal package design and quality assurance aspects. BAM has compiled the guideline BAM-GGR 023 for the implementation of ageing assessment and related measures into the approval procedure.&#13;
The implementation of ageing management measures is obligatory in case of extension/renewal of package design approval certificates. BAM has evaluated package designs which are used only for transport as well as package designs for long term interim storage. The assessment of ageing mechanisms associated with the identification of ageing effects on components is the main part of the ageing management plan (AMP). Different approaches regarding AMP structure are introduced. Experiences and approaches about the evaluation of components for the expected package operating time are shown. We are focusing the evaluations of proofs for not accessible and not replaceable components. Operational experiences for these package designs are available and should be considered in the ageing evaluation. Corresponding measures for package monitoring are to be derived based on these results. The measures for monitoring shall be fixed in the Ageing Surveillance Program (ASP) to maintain a specification conform package for the transport on public routes. We show exemplary how results from ageing evaluation during the approval procedure are transferred into the ASP.</abstract>
    <parentTitle language="eng">Proceedings of the 21st International  Symposium on the Packaging and Transportation  of Radioactive Material</parentTitle>
    <enrichment key="eventName">PATRAM 2025</enrichment>
    <enrichment key="eventPlace">San Antonio, Texas , US</enrichment>
    <enrichment key="eventStart">27.07.2025</enrichment>
    <enrichment key="eventEnd">01.08.2025</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="opus.doi.autoCreate">false</enrichment>
    <enrichment key="opus.urn.autoCreate">true</enrichment>
    <author>Sven Schubert</author>
    <author>Martin Neumann</author>
    <author>Adrian Reichardt</author>
    <author>Steffen Komann</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>RAM</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing management</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive material</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
    <collection role="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>789</id>
    <completedYear/>
    <publishedYear>1999</publishedYear>
    <thesisYearAccepted/>
    <language>mul</language>
    <pageFirst>159</pageFirst>
    <pageLast>164</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName>VDI-Verl.</publisherName>
    <publisherPlace>Düsseldorf</publisherPlace>
    <creatingCorporation>Gesellschaft Mess- und Regelungstechnik / Gemeinschaft Experimentelle Spannungsanalyse</creatingCorporation>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="mul">Messung von Transportbeanspruchungen im Fährverkehr</title>
    <parentTitle language="mul">Anspruch und Tendenzen in der experimentellen Strukturmechanik</parentTitle>
    <identifier type="old">252</identifier>
    <identifier type="isbn">3-18-091463-7</identifier>
    <identifier type="issn">0083-5560</identifier>
    <note>Sprachen: Deutsch/Englisch - Languages: German/English</note>
    <enrichment key="eventName">GESA-Symposium 1999</enrichment>
    <enrichment key="eventPlace">Warnemünde, Deutschland</enrichment>
    <enrichment key="eventStart">1999-05-06</enrichment>
    <enrichment key="eventEnd">1999-05-07</enrichment>
    <author>Norbert Mayer</author>
    <author>Michael Kammermeier</author>
    <author>Sven Schubert</author>
    <subject>
      <language>mul</language>
      <type>uncontrolled</type>
      <value>Transportbeanspruchungen im Fährverkehr</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Weder Datei noch physisches Exemplar vorhanden ("No Access")</collection>
  </doc>
  <doc>
    <id>60186</id>
    <completedYear/>
    <publishedYear>2024</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>1</pageFirst>
    <pageLast>8</pageLast>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume>2024</volume>
    <type>conferenceobject</type>
    <publisherName>Nuclear Institute</publisherName>
    <publisherPlace>London</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Ageing management measures of transport packages for radioactive materials</title>
    <abstract language="eng">The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled.&#13;
BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements.&#13;
The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport.&#13;
The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance.</abstract>
    <parentTitle language="eng">Proceedings of Conference RAMTRANS 2024</parentTitle>
    <enrichment key="eventName">RAMTRANS 2024</enrichment>
    <enrichment key="eventPlace">London,  United Kingdom</enrichment>
    <enrichment key="eventStart">15.05.2024</enrichment>
    <enrichment key="eventEnd">17.05.2024</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <author>Sven Schubert</author>
    <author>Steffen Komann</author>
    <author>Martin Neumann</author>
    <author>Adrian Reichardt</author>
    <author>Lars Müller</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive Materials</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing Management</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport Packages</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Dual Purpose Casks</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</collection>
    <collection role="themenfelder" number="">Energie</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
    <collection role="literaturgattung" number="">Graue Literatur</collection>
    <collection role="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>60177</id>
    <completedYear/>
    <publishedYear>2024</publishedYear>
    <thesisYearAccepted/>
    <language>eng</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="eng">BAM-GGR 023 - Ageing Management for CA Approved RAM Transport Packages</title>
    <abstract language="eng">The consideration of ageing mechanisms is with integration into the IAEA-requirements now obligatory for the design of transport packages. For packages intended to be used for shipment after storage the consideration of the effects of ageing mechanisms during storage in safety analyses and the implementation of corresponding instructions for operation and maintenance are required. Therefore, these packages have been maintained during storage in a manner that all requirements specified in the IAEA-requirements and in the applicable certificates of approval have been fulfilled.&#13;
BAM is the competent authority in Germany for evaluating the thermal and mechanical design of packages for the transport of radioactive materials. In this context, BAM also evaluates the aging mechanisms and aging effects occurring during the long-term storage period of such transport packages. BAM has developed a guideline for the implementation of ageing assessment and of the measures for ageing management into the approval procedure based on IAEA-requirements.&#13;
The goal of the presented paper is to introduce this guideline and the general approach for ageing management requirements and to describe the application to a specific package design. The type and amount of the ageing management not only depend on the use of the packaging, but also on the accessibility of the components that are considered in the ageing assessment. The different operating phases of a packaging are considered for the ageing assessment, such as loading, interim storage or transport.&#13;
The implementation of measures for ageing management is divided into three levels – systemic measures, package design related measures and documentation. The systemic measures are attributed to the general management system and define the whole activities for organization of ageing management like structure, responsibilities, documentation, reports and evaluation. The package design related measures are defined in an ageing management plan. These measures shall ensure that the anticipated changes of the package design under consideration of ageing effects still complies with the design approval specification. Therefore, an ageing surveillance program and, if necessary, a gap analysis program shall be developed. The ageing management documentation ensures the continuous documentation of the compliance of a specific package to the approved package design, comprising mainly records resulting from operation and surveillance.</abstract>
    <enrichment key="eventName">RAMTRANS 2024</enrichment>
    <enrichment key="eventPlace">London, United Kingdom</enrichment>
    <enrichment key="eventStart">15.05.2024</enrichment>
    <enrichment key="eventEnd">17.05.2024</enrichment>
    <enrichment key="opus.source">publish</enrichment>
    <enrichment key="opus.doi.autoCreate">false</enrichment>
    <enrichment key="opus.urn.autoCreate">true</enrichment>
    <author>Sven Schubert</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive Materials</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Ageing Management</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport Packages</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Dual Purpose Casks</value>
    </subject>
    <collection role="ddc" number="621">Angewandte Physik</collection>
    <collection role="institutes" number="">3 Gefahrgutumschließungen; Energiespeicher</collection>
    <collection role="institutes" number="">3.3 Sicherheit von Transportbehältern</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="themenfelder" number="">Kerntechnische Entsorgung</collection>
  </doc>
  <doc>
    <id>29244</id>
    <completedYear/>
    <publishedYear>2012</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>149</pageFirst>
    <pageLast>152</pageLast>
    <pageNumber/>
    <edition/>
    <issue>3-4</issue>
    <volume>23</volume>
    <type>article</type>
    <publisherName>Ramtrans Publ.</publisherName>
    <publisherPlace>Ashford</publisherPlace>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Verification of activity release compliance with regulatory limits within spent fuel transport cask assessment</title>
    <abstract language="eng">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.</abstract>
    <parentTitle language="eng">Packaging, transport, storage &amp; security of radioactive materials (RAMTRANS)</parentTitle>
    <identifier type="old">32152</identifier>
    <identifier type="doi">10.1179/1746510913Y.0000000012</identifier>
    <identifier type="issn">1746-5095</identifier>
    <identifier type="issn">1746-5109</identifier>
    <identifier type="issn">0957-476X</identifier>
    <author>Annette Rolle</author>
    <author>Bernhard Droste</author>
    <author>Sven Schubert</author>
    <author>Ulrich Probst</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Containment compliance</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Seals</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Regulations</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Activity release</value>
    </subject>
    <collection role="literaturgattung" number="">Verlagsliteratur</collection>
    <collection role="fulltextaccess" number="">Datei im Netzwerk der BAM verfügbar ("Closed Access")</collection>
  </doc>
  <doc>
    <id>49059</id>
    <completedYear/>
    <publishedYear>2019</publishedYear>
    <thesisYearAccepted/>
    <language>eng</language>
    <pageFirst>Paper 1128, 1</pageFirst>
    <pageLast/>
    <pageNumber/>
    <edition/>
    <issue/>
    <volume/>
    <type>conferenceobject</type>
    <publisherName/>
    <publisherPlace/>
    <creatingCorporation/>
    <contributingCorporation/>
    <belongsToBibliography>0</belongsToBibliography>
    <completedDate>--</completedDate>
    <publishedDate>--</publishedDate>
    <thesisDateAccepted>--</thesisDateAccepted>
    <title language="eng">Requirements for management systems for manufacturing of transport packages: the new revision of BAM-GGR 011 guideline</title>
    <abstract language="eng">In accordance with IAEA SSR-6 para 306 a management system shall be established and implemented to ensure compliance with the relevant provisions of the IAEA regulations. BAM has issued an update of the guideline: the BAM-GGR 011. The new revision describes necessary quality assurance measures for design, manufacture, testing, documentation, use, maintenance and inspection of packagings for package designs requiring competent authority approval for the transport of radioactive material.&#13;
The measures can be categorised as system-related and design-related. They are independently approved and monitored by the German competent authority BAM and its authorised expert (BAM/T). The qualification of the organisation applying for the design approval certificate is reviewed in the context of the design approval procedure. The quality assurance measures for manufacture consist of three main steps. Pre-assessment of manufacturing documents such as quality plans, specifications etc., Manufacturing inspections according the pre-assessed documents and inspection before commissioning including documentation review. Periodic inspections during operation as well as relevant specifications for use and maintenance ensure that the properties specified in the approval certificate are preserved over the package life time. Special provisions for the return on &#13;
experience regarding operational feedback for design, manufacture, use, maintenance and inspection are given. Special focus shall be given here to the rearranged and meanwhile established system of manufacturing inspections.  This   includes   more  transparent roles  for   a)  the  Producers authorised  inspection 11282 representative, b) the independent inspection expert (S), acting on behalf of the manufacturer with acceptance of BAM, and c) BAM or its authorised expert (BAM/T). Additional attention shall be drawn to the management of deviations during manufacturing and provisions for maintenance and periodic inspections.</abstract>
    <parentTitle language="eng">Proceedings of the 19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019</parentTitle>
    <enrichment key="eventName">19th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM 2019</enrichment>
    <enrichment key="eventPlace">New Orleans, LA, USA</enrichment>
    <enrichment key="eventStart">04.08.2019</enrichment>
    <enrichment key="eventEnd">09.08.2019</enrichment>
    <author>Martin Neumann</author>
    <author>O. Schilling</author>
    <author>Christian Kuschke</author>
    <author>A. Darnstädt</author>
    <author>Sven Schubert</author>
    <author>U. Günther</author>
    <author>Frank Wille</author>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Quality assurance</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Transport</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Manufacturing</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Surveillance</value>
    </subject>
    <subject>
      <language>eng</language>
      <type>uncontrolled</type>
      <value>Radioactive material</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>
</export-example>
