Subchannel Reactor Studies: Applications and Advances Using Lattice Boltzmann Method—Comprehensive Review Study
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| Publicado en: | Fluids vol. 10, no. 5 (2025), p. 109 |
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| Autor principal: | |
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| Publicado: |
MDPI AG
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| Acceso en línea: | Citation/Abstract Full Text + Graphics Full Text - PDF |
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| 001 | 3211943992 | ||
| 003 | UK-CbPIL | ||
| 022 | |a 2311-5521 | ||
| 024 | 7 | |a 10.3390/fluids10050109 |2 doi | |
| 035 | |a 3211943992 | ||
| 045 | 2 | |b d20250101 |b d20251231 | |
| 100 | 1 | |a Abutiatey, Eugene |u Department of Nanoscience and Engineering, Inje University, 197 Inje-ro, Gimhae-si 50834, Gyeongsangnam-do, Republic of Korea; nanakwesi@oasis.inje.ac.kr | |
| 245 | 1 | |a Subchannel Reactor Studies: Applications and Advances Using Lattice Boltzmann Method—Comprehensive Review Study | |
| 260 | |b MDPI AG |c 2025 | ||
| 513 | |a Journal Article | ||
| 520 | 3 | |a Computational fluid dynamics (CFD) is an instrumental tool used in tackling the challenges of flow behavior and safety within nuclear reactor cores. Traditional CFD methods like finite volume, finite element, and finite difference have driven significant progress in nuclear engineering, particularly in single-phase and two-phase flow modeling, multiscale analysis, and multiphysics coupling. However, the Lattice Boltzmann Method (LBM), an advancing CFD tool for nuclear reactor subchannel study, remains underexplored in this field. LBM takes a unique mesoscopic approach by modeling particle distributions on a discrete lattice, offering a bridge between microscopic dynamics and macroscopic continuum behavior. Since the integration of LBM into the Lattice Bhatnagar–Gross–Krook (LBGK) model, it has significantly advanced, proving its efficiency in handling complex flow conditions. This review explores the potential of LBM in nuclear reactor subchannel applications. This study emphasizes LBM as a robust computational tool for subchannel study by highlighting its strengths, limitations, and future possibilities. | |
| 653 | |a Finite volume method | ||
| 653 | |a Principles | ||
| 653 | |a Hydrodynamics | ||
| 653 | |a Reactors | ||
| 653 | |a Fluid dynamics | ||
| 653 | |a Modelling | ||
| 653 | |a Finite difference method | ||
| 653 | |a Reactor cores | ||
| 653 | |a Nuclear reactors | ||
| 653 | |a Two phase flow | ||
| 653 | |a Nuclear engineering | ||
| 653 | |a Efficiency | ||
| 653 | |a Heat transfer | ||
| 653 | |a Simulation | ||
| 653 | |a Nuclear energy | ||
| 653 | |a Energy conservation | ||
| 653 | |a Viscosity | ||
| 653 | |a Alternative energy | ||
| 653 | |a Nuclear safety | ||
| 653 | |a Multiscale analysis | ||
| 653 | |a Finite element analysis | ||
| 653 | |a Computational fluid dynamics | ||
| 653 | |a Emission standards | ||
| 653 | |a Multiphase flow | ||
| 653 | |a Software | ||
| 653 | |a Nuclear accidents & safety | ||
| 700 | 1 | |a Chung Pil-Seung |u Department of Energy Engineering, Inje University, 197 Inje-ro, Gimhae-si 50834, Gyeongsangnam-do, Republic of Korea | |
| 773 | 0 | |t Fluids |g vol. 10, no. 5 (2025), p. 109 | |
| 786 | 0 | |d ProQuest |t Materials Science Database | |
| 856 | 4 | 1 | |3 Citation/Abstract |u https://www.proquest.com/docview/3211943992/abstract/embedded/75I98GEZK8WCJMPQ?source=fedsrch |
| 856 | 4 | 0 | |3 Full Text + Graphics |u https://www.proquest.com/docview/3211943992/fulltextwithgraphics/embedded/75I98GEZK8WCJMPQ?source=fedsrch |
| 856 | 4 | 0 | |3 Full Text - PDF |u https://www.proquest.com/docview/3211943992/fulltextPDF/embedded/75I98GEZK8WCJMPQ?source=fedsrch |