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dc.contributor.authorEleme, Z.
dc.contributor.authorOgállar Ruiz, Francisco
dc.contributor.authorPorras Sánchez, José Ignacio 
dc.contributor.authorPraena Rodríguez, Antonio Javier 
dc.contributor.authorTorres Sánchez, Pablo 
dc.date.accessioned2021-05-05T07:27:20Z
dc.date.available2021-05-05T07:27:20Z
dc.date.issued2020-09-30
dc.identifier.citationEPJ Web of Conferences 239, 05014 (2020). [https://doi.org/10.1051/epjconf/202023905014]es_ES
dc.identifier.urihttp://hdl.handle.net/10481/68315
dc.descriptionThis research is co-financed by Greece and the European Union (European Social Fund-ESF) through the Operational Programme Human Resources Development, Education and Lifelong Learning in the context of the project "Strengthening Human Resources Research Potential via Doctorate Research" (MIS-5000432), implemented by the State Scholarships Foundation (IKY). Also, the authors would like to acknowledge the support of the European Commission under the CHANDA project (7th Framework Programme).es_ES
dc.description.abstractFeasibility, design and sensitivity studies on innovative nuclear reactors that could address the issue of nuclear waste transmutation using fuels enriched in minor actinides, require high accuracy cross section data for a variety of neutron-induced reactions from thermal energies to several tens of MeV. The isotope Am-241 (T-1/2= 433 years) is present in high-level nuclear waste (HLW), representing about 1.8 % of the actinide mass in spent PWR UOx fuel. Its importance increases with cooling time due to additional production from the beta-decay of Pu-241 with a half-life of 14.3 years. The production rate of 241Am in conventional reactors, including its further accumulation through the decay of Pu-241 and its destruction through transmutation/incineration are very important parameters for the design of any recycling solution. In the present work, the Am-241(n,f) reaction cross-section was measured using Micromegas detectors at the Experimental Area 2 of the n_TOF facility at CERN. For the measurement, the U-235(n,f) and U-238(n,f) reference reactions were used for the determination of the neutron flux. In the present work an overview of the experimental setup and the adopted data analysis techniques is given along with preliminary results.es_ES
dc.description.sponsorshipEuropean Union (European Social Fund-ESF) through the Operational Programme Human Resources Development, Education and Lifelong Learning MIS-5000432es_ES
dc.description.sponsorshipEuropean Commission under the CHANDA project (7th Framework Programme)es_ES
dc.language.isoenges_ES
dc.publisherEDP Scienceses_ES
dc.rightsAtribución 3.0 España*
dc.rights.urihttp://creativecommons.org/licenses/by/3.0/es/*
dc.titleFirst results of the Am-241(n,f) cross section measurement at the Experimental Area 2 of the n_TOF facility at CERNes_ES
dc.typeinfo:eu-repo/semantics/conferenceObjectes_ES
dc.rights.accessRightsinfo:eu-repo/semantics/openAccesses_ES
dc.identifier.doi10.1051/epjconf/202023905014
dc.type.hasVersioninfo:eu-repo/semantics/publishedVersiones_ES


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Atribución 3.0 España
Except where otherwise noted, this item's license is described as Atribución 3.0 España