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dc.contributor.authorParadela, C.
dc.contributor.authorDurán, I.
dc.contributor.authorTassan Got, Laurence
dc.contributor.authorCalviño Tavares, Francisco
dc.contributor.authorCortés Rossell, Guillem Pere
dc.contributor.authorPretel Sánchez, Carme
dc.contributor.otherUniversitat Politècnica de Catalunya. Departament de Física
dc.identifier.citationParadela, C., Durán, I., Tassan, L., Calviño, F., Cortes, G., Pretel, C. High accuracy 235U(n,f) data in the resonance energy region. A: International Workshop on Nuclear Data Evaluation for Reactor Applications. "EPJ Web of Conferences, vol. 111, 2016". Aix-en-Provence: EDP Sciences, 2015, p. 1-6.
dc.description.abstractThe 235U neutron-induced cross section is widely used as reference cross section for measuring other fission cross sections, but in the resonance region it is not considered as an IAEA standard because of the scarce experimental data covering the full region. In this work, we deal with a new analysis of the experimental data obtained with a detection setup based on parallel plate ionization chambers (PPACs) at the CERN n_TOF facility in the range from 1 eV to 10 keV. The relative cross section has been normalised to the IAEA value in the region between 7.8 and 11 eV, which is claimed as well-known. Comparison with the ENDF/B-VII evaluation and the IAEA reference file from 100 eV to 10 keV are provided.
dc.format.extent6 p.
dc.publisherEDP Sciences
dc.rightsAttribution-NonCommercial-NoDerivs 3.0 Spain
dc.subjectÀrees temàtiques de la UPC::Energies::Energia nuclear
dc.subjectÀrees temàtiques de la UPC::Física
dc.subject.lcshNuclear reactions
dc.subject.otherCross section
dc.subject.otherNuclear reaction
dc.titleHigh accuracy 235U(n,f) data in the resonance energy region
dc.typeConference lecture
dc.subject.lemacReaccions nuclears
dc.contributor.groupUniversitat Politècnica de Catalunya. ANT - Advanced Nuclear Technologies Research Group
dc.rights.accessOpen Access
dc.description.versionPostprint (published version)
dc.relation.projectidinfo:eu-repo/grantAgreement/MICINN/1PE/ FPA2011-28770-C03-03
upcommons.citation.authorParadela, C., Durán, I., Tassan, L., Calviño, F., Cortes, G., Pretel, C.
upcommons.citation.contributorInternational Workshop on Nuclear Data Evaluation for Reactor Applications
upcommons.citation.publicationNameEPJ Web of Conferences, vol. 111, 2016

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