NTHAS 14 (14th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety)

Tracks

Invitation to Submit

The NTHAS14 Technical Program Committee is calling for contributed papers on nuclear thermal hydraulics and safety in the following general subject areas:

  • Thermal Hydraulics Fundamentals
  • Two-Phase Flow Experiments and Analysis
  • CHF and Post-CHF Heat Transfer
  • Instrumentation and Measurement Techniques
  • Fluid-Structure interactions
  • Computational Fluid Dynamics and Heat Transfer
  • Code Development and V&V
  • Severe Accident Experiments and Analysis
  • Spent Fuel Management and Decommissioning Safety
  • Hydrogen Behavior and Combustion
  • Water Reactor Thermal Hydraulics and Safety
  • Liquid Metal Reactor Thermal Hydraulics and Safety
  • Gas Cooled Reactor Thermal Hydraulics and Safety
  • Molten Salt Reactor Thermal Hydraulics and Safety
  • Fusion Reactor Thermal Hydraulics and Safety
  • Thermal Hydraulic Aspects of Plant Operation
  • Heat Exchanger Design and Turbomachinery
  • Probabilistic Safety Assessment (PSA)
  • Application of AI Technology for TH

Symposium Support Office

JTB Corp.
Western Japan MICE Branch