ALFREDO YUUITIRO ABE
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Artigo IPEN-doc 29915 Best estimate plus uncertainty analysis of metal-water reaction transient experiment2023 - AVELAR, ALAN M.; DINIZ, CAMILA; CAMARGO, FÁBIO de; GIOVEDI, CLAUDIA; ABE, ALFREDO; CHERUBINI, MARCO; PETRUZZI, ALESSANDRO; MOURÃO, MARCELO B.Uncertainty analysis is applied in the licensing process for nuclear installations to complement best estimate analysis and to verify that the upper bound value is less than the threshold corresponding to the safety parameter of interest. Metal-water reaction is a critical safety phenomenon of water-cooled nuclear reactors at accident conditions, e.g. Loss-Of-Coolant Accidents (LOCA). AISI 348 cladding is able to increase the accident tolerance comparing to Zr-based alloys and differently from other accident tolerant fuel cladding options, there is operational experience of nuclear power plants with stainless steel. In this study, a transient oxidation experiment of AISI 348 by steam was conducted and the major sources of uncertainty were addressed. An evaluation model was developed to calculate the evolution of mass gain during the experiment. Meanwhile, uncertainty propagation of experimental data was performed. The results show that the mass gain predicted by the transient metal-water reaction model lays within the experimental data uncertainty band. Furthermore, the selection of the oxidation kinetics model seems to be important whether the analysis wills to provide conservative results.Artigo IPEN-doc 29914 Assessment of minimum allowable thickness of advanced steel (FeCrAl) cladding for accident tolerant fuel2023 - ABE, ALFREDO; GIOVEDI, CLAUDIA; MELO, CAIO; SILVA, ANTONIO T. eThe ferritic iron-chromium-aluminum (FeCrAl) alloy cladding is considered to be the most promising for near-term application in the ATF framework to replace existing zirconium alloy cladding. Although FeCrAl cladding presents several advantages, it is well known that there are at least two main drawbacks, one is the increased thermal neutron absorption cross-section compared to the current Zr-based cladding resulting in a neutronic penalty and another is tritium higher permeation. In the present study, the minimum allowable thickness of cladding is addressed considering neutronic penalty reduction and the mechanical-structural behavior under the LOCA accident condition. The neutronic penalty assessment was performed using the Monte Carlo code and mechanical-structural performance of the FeCrAl cladding using the TRANSURANUS fuel code, which was modified to consider properly the FeCrAl cladding.Tese IPEN-doc 29731 Análise neutrônica e do comportamento sob irradiação de combustíveis tolerantes à falha2023 - ABE, ALFREDO Y.O presente trabalho apresenta uma avaliação e análise quanto aos aspectos neutrônicos e de desempenho de combustível para os potenciais candidatos a combustíveis tolerantes a falha (ATF). Na fase inicial do trabalho para o levantamento bibliográfico utilizou-se a metodologia baseada na técnica de maturidade tecnológica (TRL) para avaliar as diversas opções e tecnologias desses combustíveis. Esta fase inicial permitiu identificar nos desenvolvimentos dos combustíveis tolerantes a falha as principais lacunas e as atividades necessárias para a obtenção e utilização comercial em reatores de potência. As avaliações e as análises neutrônica e de desempenho do combustível dos principais candidatos à combustíveis tolerantes a falha foram realizadas por meio de simulações computacionais utilizando programas de desempenho do combustível (TRANSURANUS) e neutrônica (SERPENT). As atividades consistiram na avaliação e verificação de um projeto de núcleo de reator constituído de combustíveis tolerantes a falha (combustíveis: UO2, U3Si2, UN, UO2-BeO) e os revestimentos: ZIRLO, SiC, FeCrAl, AISI-348). Para tanto, foram obtidos e avaliados os principais parâmetros associados ao projeto do núcleo do reator. Além disso, o trabalho envolveu a avaliação de desempenho de um dos revestimentos (FeCrAl) do combustível tolerantes a falha mais promissores considerando as condições de operação normal e em cenário de acidente. Como conclusão preliminar das atividades desenvolvidas neste trabalho destaca-se a viabilidade neutrônica dos diferentes combustíveis ATF, no entanto em termos de desempenho do combustível nem todas as opções disponíveis ainda possuem grau de maturidade suficiente para aplicação na indústria nuclear em curto e médio prazo. Destaca-se que este trabalho aborda e busca contribuir com um tema bastante atual e relevante na comunidade nuclear, principalmente os grandes desafios envolvidos no desenvolvimento, fabricação e o licenciamento dos combustíveis tolerantes a falha junto aos órgãos regulatórios.Artigo IPEN-doc 29620 Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance2023 - AVELAR, ALAN M.; CAMARGO, FABIO de; SILVA, VANESSA S.P. da; GIOVEDI, CLAUDIA; ABE, ALFREDO; MOURAO, MARCELO B.This study investigates the high temperature oxidation behaviour of a Ni–20Cr-1.2Si (wt.%) alloy in steam from 1200 °C to 1350 °C by Thermogravimetric Analysis (TGA), Scanning Electron Microscopy (SEM), Energy Dispersive X-ray Spectroscopy (EDS) and X-ray Diffraction (XRD). The results demonstrate that exposed Ni-based alloy developed a thin oxide scale, consisted mainly of Cr2O3. The oxidation kinetics obtained from the experimental results was applied to evaluate the hydrogen generation considering a simplified reactor core model with different cladding alloys following an unmitigated Loss-Of-Coolant Accident (LOCA) scenario in a hypothetical Small Modular Reactor (SMR). Overall, experimental data and simulations results show that both Fe-based and Ni-based alloys may enhance cladding survivability, delaying its melting, as well as reducing hydrogen generation under accident conditions compared to Zr-based alloys. However, a substantial neutron absorption occurs when Ni-based alloys are used as cladding for current uranium-dioxide fuel systems, even when compared to Fe-based alloys.Artigo IPEN-doc 29118 Passive Autocatalytic Recombiner perfomance assessment using COCOSYS2022 - GALVAO, H.P.; SHORTO, J.M.B.; SOBRINHO, G.T.; ABE, A.Y.; GIOVEDI, C.The progression of severe accidents in nuclear reactors is characterized by a diversity of phenomena that are Beyond Design Basis (BDBA), such as Direct Containment Heating (DCH), Molten Corium Concrete Interaction (MCCI), hydrogen detonation, and others. Currently, there are several devices and systems that allow mitigating the progression of these events, avoiding the failure of the physical barriers between the nuclear power plant and the environment. In this context, the present work aims to reproduce the HR-14 experiment carried out at the Thermal-hydraulic, Hydrogen, Aerosols and Iodine (THAI) test facility through the Passive Autocatalytic Recombiners (PAR) performance assessment with the COCOSYS code. The analysis of the convergence of the results was performed using the Fast Fourier Transform Based Method (FFTBM) and showed that the results had sufficient accuracy with the experimental data.Artigo IPEN-doc 28287 The FeCrAl cladding assessment under accident condition using TRANSURANUS fuel performance code2021 - ABE, ALFREDO; MELLO, CAIO; SANTOS, TAMIRYS; GIOVEDI, CLAUDIAArtigo IPEN-doc 28256 Passive Autocatalytic Recombiner perfomance assessment using COCOSYS code2021 - GALVAO, H.P.; SHORTO, J.M.B.; SOBRINHO, G.T.; ABE, A.Y.; GIOVEDI, CArtigo IPEN-doc 27963 Preliminary assessment of iron alloy cladding as accident tolerant fuel cladding2019 - ABE, ALFREDO; TEIXEIRA, ANTONIO; SOUZA, DANIEL; GIOVEDI, CLAUDIAArtigo IPEN-doc 27926 Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario2021 - GIOVEDI, C.; ABE, A.; MUNIZ, R.O.R.; GOMES, D.S.; SILVA, A.T.; MARTINS, M.R.Accident tolerant fuels (ATF) has been studied since the Fukushima Daiichi accident in the research efforts to develop new materials which under accident scenarios could maintain the fuel rod integrity for a longer period compared to the cladding and fuel system usually utilized in Pressurized Water Reactors (PWR). The efforts have been focused on new materials applied as cladding, then iron-base alloys appear as a possible candidate. The aim of this paper is to implement modifications in FRAPCON and FRAPTRAN fuel performance codes to evaluate the behavior of iron-based alloys under Loss-of-Coolant Accident (LOCA) scenario. For this, initially the properties related to the thermal and mechanical behavior of iron-based alloys were obtained from the literature, appropriately adapted and introduced in the fuel performance code subroutines. The adopted approach was step by step modifications, where different versions of the code were created. The assessment of the implemented modification was carried out simulating an experiment available in the open literature (IFA-650.5) related to zirconium-based alloy fuel rods submitted to LOCA conditions. The obtained results for the iron-based alloy were compared to those obtained using the regular version of the fuel performance code for zircaloy-4. The obtained results have shown that the most important properties to be changed are those from the subroutines related to the mechanical properties of the cladding. The results obtained have shown that the burst is observed at a longer time for fuel rods with iron-based alloy, indicating the potentiality of this material to be used as cladding with ATF purposes.Capítulo IPEN-doc 27693 Neutronic screening of potential candidate for accident tolerant fuel2020 - ABE, ALFREDO; GIOVEDI, CLAUDIA; MARTINS, M.