Full metadata record
DC FieldValueLanguage
dc.contributor.authorCAPRIOTTI LUCAen_GB
dc.contributor.authorINAGAKI KENTAen_GB
dc.contributor.authorPAPAIOANNOU Dimitriosen_GB
dc.contributor.authorBREMIER Stephanen_GB
dc.contributor.authorOHTA Hirokazuen_GB
dc.contributor.authorOGATA Ten_GB
dc.contributor.authorELOIRDI Rachelen_GB
dc.contributor.authorBOCCI Fabioen_GB
dc.contributor.authorBOUEXIERE Danielen_GB
dc.contributor.authorRONDINELLA Vincenzoen_GB
dc.date.accessioned2014-11-28T01:03:29Z-
dc.date.available2014-11-27en_GB
dc.date.available2014-11-28T01:03:29Z-
dc.date.created2014-11-17en_GB
dc.date.issued2014en_GB
dc.date.submitted2014-01-16en_GB
dc.identifier.citationAmerican Nuclear Society Annual Meeting 2014: Proceedingsen_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC88447-
dc.description.abstractClosed nuclear fuel cycles, based on separation from spent fuel and subsequent recycling of Pu, U as fuel, and transmutation of Minor Actinides (MA) Np, Am, Cm, are developed worldwide to ensure sustainable energy supplies while minimizing the long-term radiotoxicity of the resulting high level waste. METAPHIX is a collaboration project between the Central Research Institute of Electric Power Industry (CRIEPI, Japan) and the Institute for Transuranium Elements (ITU, part of the Joint Research Centre of the European Commission). The project studies safety and performance of fast reactor metal fuels containing MA; safety of all stages of a closed nuclear fuel cycle are considered. Nine Na-bonded fuel pins loaded with four U-Pu-Zr-based alloy compounds were fabricated in ITU. Two compounds contained Rare Earths (RE: Y, Ce, Nd, Gd) in addition to MA, reproducing the output of pyrometallurgical reprocessing of LWR spent fuel. Base alloy U-19Pu-10Zr fuel was also included as reference. Unirradiated METAPHIX fuel samples characterization complements post irradiation examination and contributes to deeper understanding of the irradiation effects on phase composition and distribution in the metal alloy fuel containing MA and RE. Comparative phase analysis on unirradiated and low and medium burnup fuel samples are performed, together with other thermo-physical studies. The results obtained so far confirm the overall positive irradiation behaviour of MA-containing alloy fuel, in line with that of conventional U-Pu-Zr.en_GB
dc.description.sponsorshipJRC.E.2-Safety of Irradiated Nuclear Materialsen_GB
dc.format.mediumCD-ROMen_GB
dc.languageENGen_GB
dc.publisherAmerican Nuclear Societyen_GB
dc.relation.ispartofseriesJRC88447en_GB
dc.titlePhase characterization in unirradiated and irradiated metallic fuel for minor actinides transmutation in fast reactoren_GB
dc.typeArticles in periodicals and booksen_GB
JRC Directorate:Nuclear Safety and Security

Files in This Item:
There are no files associated with this item.


Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.