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dc.contributor.authorRONDINELLA Vincenzoen_GB
dc.contributor.authorWISS Thierryen_GB
dc.contributor.authorMAUGERI E.en_GB
dc.contributor.authorCOLLE Jean-Yvesen_GB
dc.date.accessioned2012-05-17T00:01:09Z-
dc.date.available2012-05-16en_GB
dc.date.available2012-05-17T00:01:09Z-
dc.date.created2012-03-08en_GB
dc.date.issued2011en_GB
dc.date.submitted2011-10-13en_GB
dc.identifier.citationProceedings IHLRWMC 2011 p. 230 - 233en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC67161-
dc.description.abstractThe evolution during storage of properties relevant for safe handling/processing of high specific alpha-activity fuels and wasteforms is strongly affected by the build-up of alpha-decay damage and helium. This paper describes the alteration of properties, such as hardness, lattice parameter swelling, thermal diffusivity, monitored as a function of time, hence of accumulated damage, on various irradiated and unirradiated compounds. The integral over time of the alpha-decay effects accumulated under accelerated conditions (high specific alpha-activity) can simulate the effects of long storage times in fuels and waste forms. Experiments combining annealing studies using calorimetry techniques and He-release as a function of temperature with microstructure examination using transmission electron microscopy are performed to investigate the correlation among the annealing of defects in the microstructure, the release behavior of He, and the heat effects associated with these processes in the material. Discrete property recovery stages were identified between ~500 and ~1400 K, corresponding to the mobility of various types of defects and to a He release stage. The energy associated with these annealing steps was determined. The materials studied include LWR UO2 and MOX, and minor actinide-containing mixed oxide fuel irradiated in fast reactor. The investigation on irradiated fuel is complemented by studies on alpha-doped UO2 and ceramic matrix materials, and on natural analogues. This allows assessing the superimposition of alpha-decay effects occurring during storage at relatively low temperature on the fuel alterations occurring during in-pile irradiation. Comparative analysis of spent fuel and alpha-doped materials also allows assessing the relevance of dose rate effects on the property evolution under accelerated He/decay damage accumulation regimes. The final goal of these studies is to assess the mechanical integrity of nuclear and high level waste forms during 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.ispartofseriesJRC67161en_GB
dc.titleEFFECTS OF HELIUM BUILD-UP ON NUCLEAR FUEL EVOLUTION DURING STORAGEen_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Nuclear Safety and Security

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