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dc.contributor.authorFACCHINI Albertoen_GB
dc.contributor.authorGIUSTI Valerioen_GB
dc.contributor.authorCIOLINI Riccardoen_GB
dc.contributor.authorTUCEK Kamilen_GB
dc.contributor.authorTHOMAS DIMITRIOSen_GB
dc.contributor.authorD'AGATA Elioen_GB
dc.date.accessioned2017-01-15T01:26:31Z-
dc.date.available2017-01-13en_GB
dc.date.available2017-01-15T01:26:31Z-
dc.date.created2017-01-06en_GB
dc.date.issued2017en_GB
dc.date.submitted2016-12-05en_GB
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN vol. 313 p. 1-9en_GB
dc.identifier.issn0029-5493en_GB
dc.identifier.urihttp://www.sciencedirect.com/science/article/pii/S0029549316304472en_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC103611-
dc.description.abstractThe new reactor concepts proposed in the Generation IV International Forum require the development and validation of new components and new materials. Inside the Collaborative Project on the European Sodium Fast Reactor, several accidental scenario have been studied. Nevertheless, none of them coped with mechanical safety assessment of the fuel cladding under accidental conditions. Among the accidental conditions considered, there is the unprotected transient of overpower (UTOP), due to the insertion, at the end of the first fuel cycle, of a positive reactivity into the reactor core as a consequence of the unexpected runaway of one control rod. The goal of the study was the search for a detailed distribution of the fission power, in the radial and axial directions, within the power peaked fuel pin under the above accidental conditions. Results show that after the control rod ejection an increase from 658 W/cm3 to 894 W/cm3, i.e. of some 36%, is expected for the power peaked fuel pin. This information will represent the base to investigate, in a future work, the fuel cladding safety margin.en_GB
dc.description.sponsorshipJRC.G.I.4-Nuclear Reactor Safety and Emergency Preparednessen_GB
dc.format.mediumOnlineen_GB
dc.languageENGen_GB
dc.publisherELSEVIER SCIENCE SAen_GB
dc.relation.ispartofseriesJRC103611en_GB
dc.titleDetailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivityen_GB
dc.typeArticles in periodicals and booksen_GB
dc.identifier.doi10.1016/j.nucengdes.2016.11.014en_GB
JRC Directorate:Nuclear Safety and Security

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