THIAGO CARLUCCIO
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Relatório IPEN-doc 29650 Estimativas dos fluxos de nêutrons e gamas e doses por radiação direta em acidentes de criticalidade no CECON do IPEN para subsidiar o posicionamento dos detetores do Sistema de Alarme de Acidente de Criticalidade2023 - SHORTO, JULIAN M.B.; CARLUCCIO, THIAGOEste trabalho visa estimar o fluxo de nêutrons, o fluxo de gamas e as doses absorvidas esperadas por radiação direta instantânea em acidentes de criticalidade no Centro do Combustível Nuclear (CECON/IPEN) de forma a subsidiar o posicionamento dos detetores do Sistema de Alarme de Acidente de Criticalidade. O CECON é responsável pela produção do combustível nuclear para a operação do reator de pesquisa IEA-R1, situado no IPEN.Artigo IPEN-doc 21277 Neutron damage in the plasma chamber first wall of the GCFTR-2 fusion-fission hybrid reactor2014 - PINTO, L.N.; GONNELLI, E.; ROSSI, P.C.R.; CARLUCCIO, T.; SANTOS, A. dosThe successful development of energy-conversion machines based on either nuclear fission or fusion is completely dependent on the behaviour of the engineering materials used to construct the fuel containment and primary heat extraction systems. Such materials must be designed in order to maintain their structural integrity and dimensional stability in an environment involving high temperatures and heat fluxes, corrosive media, high stresses and intense neutron fluxes. However, despite the various others damage issues, such as the effects of plasma radiation and particle flux, the neutron flux is sufficiently energetic to displace atoms from their crystalline lattice sites. It is clear that the understanding of the neutron damage is essential for the development and safe operation of nuclear systems. Considering this context, the work presents a study of neutron damage in the Gas Cooled Fast Transmutation Reactor (GCFTR-2) driven by a Tokamak D-T fusion neutron source of 14.03 MeV. The theoretical analysis was performed by MCNP-5 and the ENDF/B-VII.1 neutron data library. A brief discussion about the determination of the radiation damage is presented, along with an analysis of the total neutron energy deposition in seven points through the material of the plasma source wall (PSW), in which was considered the HT-9 steel. The neutron flux was subdivided into three energy groups and their behaviour through the material was also examined.Artigo IPEN-doc 19917 Comparison between two gas-cooled tru burner subcritical reactors: fusion-fission and ADS2011 - CARLUCCIO, T.; ROSSI, P.C.R.; ANGELO, G.; MAIORINO, J.R.; TALAMO, A.; GOHAR, Y.Artigo IPEN-doc 21070 Preliminary neutronic assessmento for ATF (Accident Tolerant Fuel) based on iron alloy2015 - ABE, ALFREDO; CARLUCCIO, THIAGO; PIOVEZAN, PAMELA; GIOVEDI, CLAUDIA; MARTINS, MARCELOResumo IPEN-doc 15426 The utilization of MCNP code to simulate the yalina booster facility using the ADS library2006 - CARLUCCIO, T.; MAIORINO, J.R.; SANTOS, A. dosArtigo IPEN-doc 10729 A utilizacao do pacote scale para processar seccoes de choque dependente do tempo e realizar a analise de deplecao2005 - CARLUCCIO, T.; MAIORINO, J.R.Artigo IPEN-doc 10648 A review of models and codes for neutron source (spallation) calculation for ADS application2005 - MAIORINO, J.R.; MONGELLI, S.T.; SANTOS, A.; ANEFALOS, S.; DEPPMAN, A.; CARLUCCIO, T.Artigo IPEN-doc 18829 The calculation of the YALINA BOOSTER zero power sub critical assembly driven by external neutron sources: Brazilian contribution2010 - CARLUCCIO, THIAGO; ROSSI, PEDRO C.R.; MAIORINO, JOSE R.Artigo IPEN-doc 10907 Nuclear energy in Brazil and the R&D status on fast systems national report2004 - MAIORINO, J.R.; SANTOS, A.; ANEFALOS, S.; MONGELLI, S.; CARLUCCIO, T.Artigo IPEN-doc 10899 A review of thorium utilization as an option for advanced fuel cycle-potential option for Brazil in the future2004 - MAIORINO, J.R.; CARLUCCIO, T.
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