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dc.contributor.authorSIRAKOV I.en_GB
dc.contributor.authorKOPECKY Stefanen_GB
dc.contributor.authorMASSIMI C.en_GB
dc.contributor.authorMOXON M.en_GB
dc.contributor.authorPRONYAEV V. Gen_GB
dc.contributor.authorSCHILLEBEECKX Peteren_GB
dc.contributor.authorTRKOV Andrejen_GB
dc.contributor.authorVOLEV KONSTANTINen_GB
dc.contributor.authorWYNANTS Ruuden_GB
dc.date.accessioned2013-03-06T01:02:32Z-
dc.date.available2013-03-05en_GB
dc.date.available2013-03-06T01:02:32Z-
dc.date.created2013-02-28en_GB
dc.date.issued2013en_GB
dc.date.submitted2013-01-10en_GB
dc.identifier.isbn978-92-79-28421-2en_GB
dc.identifier.issn1831-9424en_GB
dc.identifier.otherEUR 25800en_GB
dc.identifier.otherOPOCE LA-NA-25800-EN-Nen_GB
dc.identifier.urihttp://publications.jrc.ec.europa.eu/repository/handle/JRC78696-
dc.description.abstractAn ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 106,108,110,111,112,113,114,116Cd. The parameters are the result of an analysis of experimental data available in the literature together with a parameter adjustment on transmission and capture data obtained at the time-of-flight facility GELINA. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluations in the resonance region with corresponding files from the JEFF-3.1.2 nuclear data library (or with the JEFF-Beta-CAD proposed evaluation in case of 113Cd). These files were produced for use in the JEFF32T2 library. For neutron induced reactions in the unresolved resonance region the JENDL-4.0 evaluation for 111Cd and 113Cd was adopted. The evaluated files have been processed with the latest updates of NJOY.99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The ACE files have been utilized to study the effect of the evaluated resonance parameters on results of integral experiments. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.en_GB
dc.description.sponsorshipJRC.D.4-Standards for Nuclear Safety, Security and Safeguardsen_GB
dc.format.mediumOnlineen_GB
dc.languageENGen_GB
dc.publisherPublications Office of the European Unionen_GB
dc.relation.ispartofseriesJRC78696en_GB
dc.titleENDF-6 compatible evaluation of neutron induced reaction cross sections for 106,108,110,111,112,113,114,116Cden_GB
dc.typeEUR - Scientific and Technical Research Reportsen_GB
dc.identifier.doi10.2787/72841en_GB
JRC Directorate:Health, Consumers and Reference Materials

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