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Investigations to predict the long term performance of polymeric components of storage casks for radioactive waste

  • As a Federal institute for materials research and testing it is part of our tasks to evaluate the safety of casks designed for transport and/or storage of radioactive material. This includes the investigation of elastomeric seals and polymeric neutron shielding materials used in the containers. In this contribution we would like to present our research focused on the long term performance and associated changes of material properties of elastomeric seals (e.g. EPDM, FKM) and neutron shielding materials ((Ultra) High Molecular Weight Polyethylene) employed in storage casks. Our approach comprises accelerated ageing investigations at elevated temperatures and to some extent investigations of irradiated materials. As the requirements for the extended use of cables in nuclear power plants and for the long term use of cask components are to a certain extent similar, our work might be of interest for the workshop on “Cables ageing in nuclear power plants; R&D current status andAs a Federal institute for materials research and testing it is part of our tasks to evaluate the safety of casks designed for transport and/or storage of radioactive material. This includes the investigation of elastomeric seals and polymeric neutron shielding materials used in the containers. In this contribution we would like to present our research focused on the long term performance and associated changes of material properties of elastomeric seals (e.g. EPDM, FKM) and neutron shielding materials ((Ultra) High Molecular Weight Polyethylene) employed in storage casks. Our approach comprises accelerated ageing investigations at elevated temperatures and to some extent investigations of irradiated materials. As the requirements for the extended use of cables in nuclear power plants and for the long term use of cask components are to a certain extent similar, our work might be of interest for the workshop on “Cables ageing in nuclear power plants; R&D current status and forecast”.zeige mehrzeige weniger

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Metadaten
Autor*innen:Matthias JaunichORCiD
Koautor*innen:Dietmar Wolff
Dokumenttyp:Vortrag
Veröffentlichungsform:Präsentation
Sprache:Englisch
Jahr der Erstveröffentlichung:2016
DDC-Klassifikation:Technik, Medizin, angewandte Wissenschaften / Ingenieurwissenschaften / Angewandte Physik
Freie Schlagwörter:Ageing; Lifetime evaluation; Neutron shielding; Rubber seal; Storage cask
Veranstaltung:Cables ageing in nuclear power plants; R&D current status and forecast
Veranstaltungsort:Rez, Czech Republic
Beginndatum der Veranstaltung:24.05.2016
Enddatum der Veranstaltung:25.05.2016
Verfügbarkeit des Dokuments:Datei im Netzwerk der BAM verfügbar ("Closed Access")
Datum der Freischaltung:03.06.2016
Referierte Publikation:Nein
Eingeladener Vortrag:Nein
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