ALFREDO YUUITIRO ABE
5 resultados
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Artigo IPEN-doc 30532 Nuclear power plants2024 - GIOVEDI, C.; ABE, A.Y.; OLIVEIRA, A.; DE MICHELI, L.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 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 27578 Oxidation of AISI 304L and 348 stainless steels in water at high temperatures2020 - AVELAR, ALAN M.; GIOVEDI, CLAUDIA; ABE, ALFREDO Y.; MOURAO, MARCELO B.Oxidation of AISI 304L and 348 stainless steels was investigated in water at 1000 – 1350 °C by TGA, SEM, EDS, and Raman spectroscopy. Linear-Parabolic kinetics and multilayer oxide scales with voids were found for both alloys. Based on the experimental results, AISI 304L presented higher oxidation resistance and higher activation energy. Zircaloy-4 kinetic results were used for validation and performance comparison. In severe accidents conditions, stainless steel might lead to a faster hydrogen production comparing to Zircaloy.Artigo IPEN-doc 27361 On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding2020 - AVELAR, ALAN M.; MOURAO, MARCELO B.; MATURANA, MARCOS; GIOVEDI, CLAUDIA; ABE, ALFREDO Y.; PEDRASSANI, RAFAELA; SU, JIANAfter Fukushima Daiichi accident, the replacement of zirconium-based fuel cladding in Light Water Reactors (LWR) became one of the main challenges of the nuclear industry. Austenitic steel–clad presents some safety advantages comparing to zirconium alloys, noticeably, higher activation energy and lower enthalpy of metal-water reaction. Thus, it produces a slower hydrogen release into the containment following a postulated accident. In this study, a Loss-of-Coolant Accident (LOCA) aggravated by the complete failure of the Emergency Core Cooling System (ECCS) is analyzed for a Small Modular Reactor (SMR). Post-accident injection of inert gas into the containment is used as one of the hydrogen control systems, to enhance safety margins during Severe Accidents (SA). The inertization system is successful in complementing Passive Autocatalytic Recombiners (PAR) to perform combustible gas control.