International Conference on Nuclear Materials and Nuclear Fuels ICNMNF on February 17-18, 2025 in Rome, Italy

Advanced Code Development and Validation / Verification / Applications
Applications of Computational Methods to Nuclear Systems
Boiling and Condensation Phenomena
CHF and Post-CHF Heat Transfer
Computational Fluid Dynamics and Heat Transfer
Computational Methods, Modelling, Verification / Validation
Experimental Methods and Instrumentation
Fluid-structure interactions
Fluid-Structures and Materials Interactions
Fusion Reactor Thermal Hydraulics and Safety
Gas Cooled Reactor Thermal Hydraulics and Safety
Generation IV and Future Innovative Nuclear Reactors Thermalhydraulics
Heat Exchanger Design and Turbo-machinery
Innovative nuclear systems and fuel cycles
Instrumentation and Measurement Techniques
Liquid Metal Reactor Thermal Hydraulics and Safety
Materials Modelling and Simulation of Nuclear Fuels
Micro-Channel Flow and Heat Transfer Phenomena
Molten Salts for Nuclear Applications
Nano-Fluid Science and Technology Applications to Nuclear Systems
Neutronics/Thermalhydraulics Coupling
Next Generation Reactor Thermalhydraulics
Nuclear education and nuclear knowledge governance
Nuclear Materials and Nuclear Security
Nuclear medicine
Nuclear Thermal Hydraulics and Safety
Radiation Stability of Complex Microstructures
Radiological safety and environment protection
Reliability, endurance and life-time resource management
Rod Bundle Thermalhydraulics
Safety Analysis and Code Development
Safety of nuclear technologies
Severe Accident Experiments and Analysis
Severe Accidents, Phenomena, Modelling and Experiments
Structural and Functional Materials for Fission Reactors
Subchannel Analysis
Thermal Hydraulics Fundamentals
Thermal-Hydraulic Aspects of Plant Operation
Thermalhydraulics and Materials Degradation Issues
Thermalhydraulics and Safety for Nuclear Reactor Plant and Core
Thermalhydraulics in Accident Management
Thermalhydraulics in Power Uprating/Life Extension
Thermalhydraulics of Non-Electricity Generating Nuclear Equipment
Thermalhydraulics of Waste Management
Thermodynamics and Thermophysics of Nuclear Fuels
Thermohydraulics and safety
Two-Phase Flow and Heat-Transfer Fundamentals
Two-Phase Flow Experiments and Analysis
Water Reactor Thermal Hydraulics and Safety