Tiago Augusto Santiago Vieira

ORCID: 0000-0001-5470-9902
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About
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Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Nuclear and radioactivity studies
  • Heat transfer and supercritical fluids
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear Physics and Applications
  • Additive Manufacturing and 3D Printing Technologies
  • Fusion materials and technologies
  • Molten salt chemistry and electrochemical processes
  • Superconducting Materials and Applications
  • Mechanical Engineering and Vibrations Research
  • Heat Transfer and Boiling Studies
  • Metallurgical Processes and Thermodynamics
  • Textile materials and evaluations
  • Advanced Battery Technologies Research
  • Cyclone Separators and Fluid Dynamics
  • Advanced Combustion Engine Technologies
  • Electrohydrodynamics and Fluid Dynamics
  • Electric and Hybrid Vehicle Technologies
  • Particle Accelerators and Free-Electron Lasers
  • Fashion and Cultural Textiles
  • Electrophoretic Deposition in Materials Science

Siemens (Germany)
2022-2024

Centro de Desenvolvimento da Tecnologia Nuclear
2020-2023

Software (Spain)
2022

National Nuclear Energy Commission
2020

The Molten Salt Fast Reactor (MSFR) represents a significant innovation within the Generation IV nuclear reactor systems, distinguished by its use of molten salt as both fuel and coolant. This study presents methodology for performing steady-state coupled neutronics thermal-hydraulics (TH) calculations using Monte Carlo (MC) Computational Fluid Dynamics (CFD) techniques. was fed with LiF base salt, thorium (232Th) fertile material 233U fissile material. Uncertainty quantification performed...

10.15392/2319-0612.2024.2643 article EN Brazilian Journal of Radiation Sciences 2025-04-23

The present study evaluates the potential implementation of two different closed fuel cycle strategies for a NuScale-like reactor core. After undergoing three burnup cycles approximately 12 MWd/kgU in initial core and five years cooling spent pool, was theoretically reprocessed using GANEX or UREX+ methods. These compositions were then mixed with thorium (Th) inserted into specific batch positions As result, proposed configurations contain assemblies loaded both conventional uranium-based...

10.15392/2319-0612.2024.2630 article EN Brazilian Journal of Radiation Sciences 2025-05-14

Abstract: This study presents a numerical investigation into the impact of various mesh element types on water flow results through representative spacer grid, utilizing Computational Fluid Dynamics (CFD). The evaluates variations k−ϵ turbulence model available in Simcenter STAR-CCM+ across different types. Three predominant cell were employed: cartesian, polyhedral, and tetrahedral, alongside three models: Standard Two-layer (STL), Realizable (RTL), Elliptic Blending (EB). analysis was...

10.15392/2319-0612.2024.2658 article EN Brazilian Journal of Radiation Sciences 2025-05-28

This paper presents the results of Computational Fluid Dynamics (CFD) oriented geometrical optimization using GeN-Foam solver applied to subchannels fuel assembly in a PWR-type nuclear reactor. is coarse mesh OpenFOAM designed study engineering problems involving coupled solution thermohydraulics, neutronics and thermomechanics. However, could be used for complex geometry simulations, enabling multi-scale simulations. To use under these conditions, code simulation had evaluated. assessment...

10.15392/2319-0612.2024.2704 article EN Brazilian Journal of Radiation Sciences 2025-05-28

In the present work, an assessment of Neutronic Benchmark Molten Salt Fast Reactor (MSFR) was performed using mesh based Monte Carlo Neutron Transport (MCNT) calculations with numerical uncertainty quantification due to discretization in neutronic parameters. Calculations Constructive Solid Geometry (CSG) models where made as a baseline for developed models. The given by utilization is evaluated extended version Grid Convergence Index (GCI). fuel salt reprocessing regarding constant rate....

10.15392/2319-0612.2023.1317 article EN cc-by Brazilian Journal of Radiation Sciences 2023-12-19

<div class="section abstract"><div class="htmlview paragraph">Simulation tools play a significant role in the automotive industry due to their cost-reducing capabilities new model development. Computational Fluid Dynamics (CFD) is extensively utilized various applications, such as vehicle aerodynamics and engine thermal management. However, its application manufacturing engineering not yet widespread. One crucial process of base coat, which provides protection for final paint...

10.4271/2023-36-0056 article EN SAE technical papers on CD-ROM/SAE technical paper series 2024-01-08

<div class="section abstract"><div class="htmlview paragraph">With the growing demand for electric vehicles (EVs), ensuring safety and efficiency of battery systems is critical. This paper presents a methodology integrating 3D Finite Element Methods (FEM) Computational Fluid Dynamics (CFD) to analyze systems, effectively mitigating thermal runaway phenomena. By combining FEM CFD, our provides comprehensive approach assess management strategies within systems. integration enables...

10.4271/2024-36-0163 article EN SAE technical papers on CD-ROM/SAE technical paper series 2024-12-20

Spacer grids are one of main components a Pressurized Water Reactor (PWR) fuel assembly. They able to improve heat transfer from rod bundles the water flow by increasing turbulence and mixture this flow. On other hand pressure drop increases because spacer grids. Experimental Computational Fluid Dynamics (CFD) analysis have been used understand how affect This is important thermal-hydraulic performance. paper aims investigate numerically experimentally through PWR The numerical experimental...

10.15392/bjrs.v8i3a.1294 article EN cc-by Brazilian Journal of Radiation Sciences 2021-02-09

In this work, a single step of coupled calculations for fuel rod IPR-R1 TRIGA was performed. The used me-thodology allowed to simulate the pin behavior in steady-state mode different power levels. aim paper is present practical approach perform between neutronic (Monte Carlo) and thermal-hydraulic (CFD) codes. For purpose, necessary evaluate influence water thermal-physical properties temperature variations on keff parameter. Besides that, Serpent Nuclear Code neutronics evaluation, while...

10.15392/bjrs.v9i2b.1295 article EN cc-by Brazilian Journal of Radiation Sciences 2021-07-25

In the present work, a numerical study of countercurrent flow limitation (CCFL) with air-water as working fluids was carried out using Computational Fluid Dynamics (CFD).The CFD code Star-CCM+ used, presenting itself robust and reliable tool for this type problem.The used geometry scaled (1:14) PWR hot leg, small deviations from experimental facility built in Centro de Desenvolvimento da Tecnologia Nuclear (CDTN).The aim work to numerically behavior system potential Loss Coolant Accident...

10.29327/vi_sencir.551829 article EN Anais da Semana Nacional de Engenharia Nuclear e da Energia e Ciências das Radiações 2022-12-23
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