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dc.contributor.authorRONDINELLA Vincenzoen_GB
dc.contributor.authorWISS Thierryen_GB
dc.contributor.authorPAPAIOANNOU Dimitriosen_GB
dc.contributor.authorNASYROW Ramilen_GB
dc.date.accessioned2013-12-20T01:01:51Z-
dc.date.available2013-12-19en_GB
dc.date.available2013-12-20T01:01:51Z-
dc.date.created2013-09-09en_GB
dc.date.issued2012en_GB
dc.date.submitted2012-10-05en_GB
dc.identifier.citationProceedings International High-Level Radioactive Waste Management Conference p. 1083 - 1088en_GB
dc.identifier.isbn978-0-89448-099-7en_GB
dc.identifier.urihttp://www.ans.org/meetings/m_154en_GB
dc.identifier.urihttp://www.ans.org/store/i_700376en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC75519-
dc.description.abstractCumulative effects associated with the alpha-decay and radiogenic helium may affect the mechanical integrity of spent fuel rods during storage and handling/transportation after storage. Accelerated decay damage build-up studies performed on unirradiated alpha-doped UO2 indicate that swelling induced in the UO2 lattice would reach a maximum at a level of damage of approximately 1.2 displacement per atom (dpa). This alpha-damage level would be reached in used UO2 fuel after one or more centuries of storage, depending on the fuel burnup and composition. Other fuel properties affected by the alpha-decay damage, such as hardness and thermal conductivity, show maximum alteration at ~0.2-0.4 dpa, corresponding to storage times of decades. The evolution of the macroscopic properties correlates with microstructure changes caused by the decay process and by the accumulation of helium. At damage levels in excess of 3 dpa, evidence is shown that the fuel microstructure undergoes restructuring and some grains subdivision is observed. This paper describes the alterations in the UO2 microstructure and the corresponding macroscopic property changes induced by the alpha-decay process as a function of time, hence of accumulated damage and helium. The range of alpha-damage considered covers short, medium and long term storage. The applicability of results obtained under conditions of accelerated decay damage accumulation to the case of used fuel rod stored for different times is discussed on the basis of comparison with irradiated UO2 and MOX data. Gaps in the available knowledge and future studies are described. The final goal of these studies is to assess the mechanical integrity of nuclear and high level waste forms during and after extended storage in view of further handling/processing.en_GB
dc.description.sponsorshipJRC.E.2-Hot cellsen_GB
dc.format.mediumCD-ROMen_GB
dc.languageENGen_GB
dc.publisherAmerican Nuclear Societyen_GB
dc.relation.ispartofseriesJRC75519en_GB
dc.titleMICROSTRUCTURE AND MACROSCOPIC ALTERATION AFFECTING NUCLEAR FUEL DURING EXTENDED STORAGEen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Nuclear Safety and Security

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