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Consideration of aging mechanism influence on transport safety of dual purpose casks for spent nuclear fuel of HLW

  • When storage of spent nuclear fuel or high level waste is carried out in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable and can be justified and certified permanently throughout that period. The effects of aging mechanisms (e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. Consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components that cannot be directly inspected or changed without opening the cask cavity, like the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging isWhen 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'.zeige mehrzeige weniger

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Autoren/innen:Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven Schubert
Dokumenttyp:Zeitschriftenartikel
Veröffentlichungsform:Verlagsliteratur
Sprache:Englisch
Titel des übergeordneten Werkes (Englisch):Packaging, transport, storage & security of radioactive materials (RAMTRANS)
Jahr der Erstveröffentlichung:2014
Organisationseinheit der BAM:3 Gefahrgutumschließungen
3 Gefahrgutumschließungen / 3.4 Sicherheit von Lagerbehältern
3 Gefahrgutumschließungen / 3.3 Sicherheit von Transportbehältern
Verlag:Ramtrans Publ.
Verlagsort:Ashford
Jahrgang/Band:25
Ausgabe/Heft:3-4
Erste Seite:105
Letzte Seite:112
Freie Schlagwörter:Aging; Aging mechanisms; Corrosion; High-level waste; Metal seals; Safety assessment; Spent fuel; Spent nuclear fuel; Storage; Transport; Transport and storage casks
DOI:https://doi.org/10.1179/1746510914Y.0000000070
ISSN:1746-5095
ISSN:1746-5109
ISSN:0957-476X
Verfügbarkeit des Dokuments:Datei im Netzwerk der BAM verfügbar ("Closed Access")
Datum der Freischaltung:20.02.2016
Referierte Publikation:Nein