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Book of Abstracts (Draft)
Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-9)
OECD Nuclear Energy Agency (NEA) Workshop
February 20-21, 2023
Thematic Areas
Thermal Hydraulics Code Development and Analysis Containment flows
Fluid-structure Interaction
Thermal fatigue
Critical Heat Flux and DNB
Pressurized Thermal Shock
Particle-laden flows
Verification and Validation
Uncertainty Quantification and CFD Best Practice Guidelines Design basis accident
Severe accident
Code coupling
Benchmarking Plant
Multiphysics Development and Applications
Reduced Order Models
Multiscale CFD and Coupling with System Codes
Machine Learning and Artificial Intelligence
Multiphase CFD
CFD for Advanced Reactors
CFD Open Source Codes