ANICCA, a computational tool for simulating nuclear fuel cycles

Ivan Merino Rodriguez, Ruber Hernandez-Garcia, Augusto Hernandez-Solis

    Research outputpeer-review

    1 Scopus citations

    Abstract

    Fuel 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.

    Original languageEnglish
    Title of host publication2020 39th International Conference of the Chilean Computer Science Society, SCCC 2020
    Publisher IEEE Computer Society and the Association for Computing Machinery
    ISBN (Electronic)9781728183282
    DOIs
    StatePublished - 16 Nov 2020
    Event2020 - SCCC: 39th International Conference of the Chilean Computer Science Society - Coquimbo
    Duration: 16 Nov 202020 Nov 2020

    Publication series

    NameProceedings - International Conference of the Chilean Computer Science Society, SCCC
    Volume2020-November
    ISSN (Print)1522-4902

    Conference

    Conference2020 - SCCC
    Country/TerritoryChile
    CityCoquimbo
    Period2020-11-162020-11-20

    ASJC Scopus subject areas

    • General Engineering
    • General Computer Science

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