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dc.contributor.authorMerino-Rodríguez, Iván
dc.contributor.authorHernández-García, Ruber
dc.contributor.authorHernández-Solís, A.
dc.date.accessioned2021-11-23T12:49:21Z
dc.date.available2021-11-23T12:49:21Z
dc.date.issued2020
dc.identifier.urihttp://repositorio.ucm.cl/handle/ucm/3509
dc.description.abstractFuel cycle simulation codes are tools developed and used worldwide to answer the many questions that arise in relation to the development or deployment of nuclear technology for electricity generation. In this context, ANICCA was developed by the Belgian Nuclear Research Center (SCK · CEN) as the tool in charge of answering these questions related to the Belgian nuclear fleet. However, the development of this tool has also turned towards research and application, expanding the range of its functionalities and technologies that can be modeled, to cover from the most basic to the most complex and advanced scenario strategies. Thus, this work presents the main features of the Nuclear Fuel Cycle Simulation Code, ANICCA, its development, operation, and future goals.es_CL
dc.language.isoenes_CL
dc.rightsAtribución-NoComercial-SinDerivadas 3.0 Chile*
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/cl/*
dc.source39th International Conference of the Chilean Computer Science Society (SCCC), 2020, 1-6es_CL
dc.subjectNuclear simulationes_CL
dc.subjectANICCAes_CL
dc.subjectNuclear fuel cyclees_CL
dc.subjectScientific computinges_CL
dc.subjectNuclear codees_CL
dc.titleANICCA, a computational tool for simulating nuclear fuel cycleses_CL
dc.typeArticlees_CL
dc.ucm.facultadFacultad de Ciencias de la Ingenieríaes_CL
dc.ucm.indexacionScopuses_CL
dc.ucm.uriieeexplore.ieee.org/document/9281233es_CL
dc.ucm.doidoi.org/10.1109/SCCC51225.2020.9281233es_CL


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