GIOVANNI LARANJO DE STEFANI

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  • Artigo IPEN-doc 26342
    Optimization on the core of IEA-R1 research reactor for enhance the radioisotopes production
    2019 - STEFANI, GIOVANNI L. de; GENEZINI, FREDERICO A.; MOREIRA, JOÃO M. de L.; SANTOS, THIAGO A. dos
    In this work a parametric study was carried out to increase the production of radioisotopes in the IEA-R1 reactor. One of the variables directly proportional to isotope production is the magnitude of the neutron flux in which some material is exposed, so the main objective of this work was to increase neutron flux, especially in the center of the reactor in the beryllium element irradiator (EIBe), within the operational and safety limits of the reactor. The study is initiated by defining a default configuration, in which core of the IEA-R1 reactor is modeled with all fresh fuel assemblies to ensure the reduction of variables that affect the data analysis, then para metric studies were performed evaluating, by comparative analysis of the behavior of the relation of neutron flux versus the fuel for the standard configuration. Therefore, another configuration was tested: the changes in the core of graphite reflecting elements for beryllium, as well as, the result due to reactor core compaction. Parameters such as the fraction of delayed neutrons (Beff) and temperature reactivity coefficient are analyzed to ensure that the configuration has the minimum safety requirements for the reactor safe operation. The results of the study demonstrate a large increase in neutron flux magnitude and in particular in the center of the nucleus in the beryllium irradiating element.
  • Artigo IPEN-doc 24698
    Consolidation of the new nuclear calculation methodology of the IEA-R1 reactor
    2017 - STEFANI, GIOVANNI L. de; CONTI, THADEU das N.
    The IEA-R1 neutron and thermo-hydraulic calculation methodology is composed of 5 computational codes from the area of reactor physics, which have a symbiotic dependence on each other. Since the outputs of each code will be used to generate the input of the next code. The programs involved in this methodology are LEOPARD, HAMMER-TECHNION, TWODB, CITATION and COBRA. Each of these codes is responsible for a specific type of calculation. In a first two-year study, between the years 2008 and 2010, these IEA-R1 nuclear reactor codes were integrated into a single management code. This management code had as main objective the reduction of the time spent by the calculation team of the reactor and to prevent against errors in the manipulation of data and data output. In this study the calculation time was reduced by 99%. The present article presents the closing of this work, being a document with the consolidation of 7 years of the use of the new calculation methodology implemented in the IEA-R1 reactor, demonstrating its efficiency and reliability, besides the proper registration of this project that had great importance Within the IPEN research reactor.
  • Resumo IPEN-doc 16229
  • Artigo IPEN-doc 16976
    Implementation of the optimization for the methodology of the neutronic calculation and thermo-hydraulic in IEA-R1 reactor
    2011 - STEFANI, GIOVANNI L. de; CONTI, THADEU das N.; SANTOS, THIAGO A. dos; FEDORENKO, GIULIANA G.; CASTRO, VINICIUS A.; MAIO, MIREIA F.