Proceedings of the 32nd International Conference on Nuclear Engineering-Volume 12; ICONE 2025, 22-26 June, Weihai, China
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Proceedings of the 32nd International Conference on Nuclear Engineering-Volume 12; ICONE 2025, 22-26 June, Weihai, China
Computational Fluid Dynamics (CFD) and Applications II
Zhu, Yanyan; Xu, Weiqiang; Tan, Sichao
Springer Verlag, Singapore
01/2026
602
Dura
Inglês
9789819534043
15 a 20 dias
Descrição não disponível.
1. Numerical analysis on heat transfer of convective LBE flow around a hemi-spherical window of spallation target.- 2. CFD for Structural Stability of Crossflow Over Tandem Cylinders.- 3. Study of Mixing Models Reflecting Local Characteristics.- 4. Numerical Simulation Study of the Dispersed Flow Region During Reflooding in Narrow Gap Channels.- 5. Numerical Simulation Study on Flow-Induced Vibration Characteristics of Single-Row and Multi-Row Helical Tube Bundles under Lead-Bismuth Fluid Flow.
Este título pertence ao(s) assunto(s) indicados(s). Para ver outros títulos clique no assunto desejado.
Nuclear Plants;Nuclear Fuel and Materials;Reactor Physics;Digital Control;Small Modular Reactors;Fusion Reactors;Nuclear Safety;Nuclear Standards;Thermal Hydraulics;Safety Analysis;Computational Fluid Dynamics;Decontamination and Decommissioning;Radiation Protection;Waste Management;Beyond Design Basis Events;Advanced Manufacturing;AI in Nuclear Science ad Technology;Computer Code Verification and Validation;Nuclear Education and Public Acceptance;Risk Assessmens and Management
1. Numerical analysis on heat transfer of convective LBE flow around a hemi-spherical window of spallation target.- 2. CFD for Structural Stability of Crossflow Over Tandem Cylinders.- 3. Study of Mixing Models Reflecting Local Characteristics.- 4. Numerical Simulation Study of the Dispersed Flow Region During Reflooding in Narrow Gap Channels.- 5. Numerical Simulation Study on Flow-Induced Vibration Characteristics of Single-Row and Multi-Row Helical Tube Bundles under Lead-Bismuth Fluid Flow.
Este título pertence ao(s) assunto(s) indicados(s). Para ver outros títulos clique no assunto desejado.
Nuclear Plants;Nuclear Fuel and Materials;Reactor Physics;Digital Control;Small Modular Reactors;Fusion Reactors;Nuclear Safety;Nuclear Standards;Thermal Hydraulics;Safety Analysis;Computational Fluid Dynamics;Decontamination and Decommissioning;Radiation Protection;Waste Management;Beyond Design Basis Events;Advanced Manufacturing;AI in Nuclear Science ad Technology;Computer Code Verification and Validation;Nuclear Education and Public Acceptance;Risk Assessmens and Management
