International Conference on Nuclear Thermal Hydraulics and Safety ICNTHS on December 13-14, 2023 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 </div>