I. M. Rodríguez, R. Hernández-García, A. Hernández-Solís
{"title":"ANICCA, a computational tool for simulating nuclear fuel cycles","authors":"I. M. Rodríguez, R. Hernández-García, A. Hernández-Solís","doi":"10.1109/SCCC51225.2020.9281233","DOIUrl":null,"url":null,"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.","PeriodicalId":117157,"journal":{"name":"2020 39th International Conference of the Chilean Computer Science Society (SCCC)","volume":"42 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2020-11-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"2020 39th International Conference of the Chilean Computer Science Society (SCCC)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/SCCC51225.2020.9281233","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1
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.