ANICCA, a computational tool for simulating nuclear fuel cycles

dc.creatorMerino-Rodríguez, Iván
dc.creatorHernández-García, Ruber
dc.creatorHernández-Solís, A.
dc.date2021-11-23T12:49:21Z
dc.date2021-11-23T12:49:21Z
dc.date2020
dc.date.accessioned2022-10-18T12:13:36Z
dc.date.available2022-10-18T12:13:36Z
dc.identifierhttp://repositorio.ucm.cl/handle/ucm/3509
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/4443713
dc.descriptionFuel 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.
dc.languageen
dc.rightsAtribución-NoComercial-SinDerivadas 3.0 Chile
dc.rightshttp://creativecommons.org/licenses/by-nc-nd/3.0/cl/
dc.source39th International Conference of the Chilean Computer Science Society (SCCC), 2020, 1-6
dc.subjectNuclear simulation
dc.subjectANICCA
dc.subjectNuclear fuel cycle
dc.subjectScientific computing
dc.subjectNuclear code
dc.titleANICCA, a computational tool for simulating nuclear fuel cycles
dc.typeArtículos de revistas


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