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Considerations of aging mechanisms influence on transport safety and reliability of dual purpose casks for spent nuclear fuel or HLW

  • When storage of spent nuclear fuel (SNF) or high-level waste (HLW) is done in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. The consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components which cannot be directly inspected or changed without opening the cask cavity, what are the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impactsWhen storage of spent nuclear fuel (SNF) or high-level waste (HLW) is done in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation, different corrosion mechanisms, stress relaxation, creep, structural changes and degradation) on the transport package design safety assessment features have to be evaluated. The consideration of these issues in the DPC transport safety case will be addressed. Special attention is given to all cask components which cannot be directly inspected or changed without opening the cask cavity, what are the inner parts of the closure system and the cask internals, like baskets or spent fuel assemblies. The design criteria of that transport safety case have to consider the operational impacts during storage. Aging is not subject of technical aspects only, but also of 'intellectual' aspects, like changing standards, scientific/ technical knowledge development and personal as well as institutional alterations. Those aspects are to be considered in the management system of the license holders and in appropriate design approval update processes. The paper addresses issues which are subject of an actual IAEA TECDOC draft 'Preparation of a safety case for a dual purpose cask containing spent nuclear fuel'.zeige mehrzeige weniger

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Metadaten
Autoren/innen:Bernhard Droste, Steffen Komann, Frank Wille, Annette Rolle, Ulrich Probst, Sven Schubert
Dokumenttyp:Beitrag zu einem Tagungsband
Veröffentlichungsform:Graue Literatur
Sprache:Englisch
Titel des übergeordneten Werkes (Englisch):PSAM 12 - Probabilistic safety assessment and management (Proceedings)
Jahr der Erstveröffentlichung:2014
Organisationseinheit der BAM:3 Gefahrgutumschließungen
3 Gefahrgutumschließungen / 3.4 Sicherheit von Lagerbehältern
3 Gefahrgutumschließungen / 3.3 Sicherheit von Transportbehältern
Erste Seite:1
Letzte Seite:10
Freie Schlagwörter:Aging mechanisms; Cesium corrosion; Closure system; Corrosion; Dual purpose casks; Metal seals; Metal seals reliability; Safety assessment; Spent fuel/high-level waste; Transport and storage casks for spent nuclear fuel or high level waste
Veranstaltung:PSAM 12 - Probabilistic safety assessment and management
Veranstaltungsort:Honolulu, Hawaii, USA
Beginndatum der Veranstaltung:22.06.2014
Enddatum der Veranstaltung:27.06.2014
URL:http://psam12.org/proceedings/paper/paper_180_1.pdf
Verfügbarkeit des Dokuments:Datei im Netzwerk der BAM verfügbar ("Closed Access")
Datum der Freischaltung:20.02.2016
Referierte Publikation:Ja
Datum der Eintragung als referierte Publikation:09.02.2015