Open Science Research Excellence

ICNMM 2021 : International Conference on Nuclear Materials and Management

Bangkok, Thailand
February 4 - 5, 2021

Call for Papers

ICNMM 2021 : International Conference on Nuclear Materials and Management is the premier interdisciplinary platform for the presentation of new advances and research results in the fields of Nuclear Materials and Management. The conference will bring together leading academic scientists, researchers and scholars in the domain of interest from around the world. Topics of interest for submission include, but are not limited to:
  • 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