Main Topics
- A-1) Thermal-hydraulics and safety of water-cooled reactors
- A-2) Thermal-hydraulics and safety of liquid-metal cooled reactors
- A-3) Thermal-hydraulics and safety of gas-cooled reactors
- A-4) Thermal-hydraulics and safety of fusion systems
- A-5) Thermal-hydraulics and safety of transmutation reactor systems
- A-6) Thermal-hydraulics and safety of molten salt reactors
- A-7) Thermal-hydraulics of supercritical fluids
- A-8) Thermal-hydraulics of heavy liquid metal
- A-9) Cross-cutting thermal-hydraulic issues of innovative nuclear systems
- B-1) Advances in experimental thermal-hydraulics
- B-2) Advances in numerical thermal-hydraulics
- B-3) Multi-scale thermal-hydraulics codes coupling
- B-4) Verification and validation of numerical codes
- B-5) CFD Application to nuclear engineering
- C-1) Plant operation and maintenance experiences
- C-2) Plant monitoring and diagnostics
- C-3) Plant simulator and operation training
- C-4) Plant life extension
- C-5) Multi-physical phenomena in nuclear operation
- C-6) Advances in materials, instrumentation and control
- D-1) Advances in nuclear safety systems and analysis
- D-2) Passive safety systems
- D-3) Severe accident mitigation measures
- D-4) Severe accident management guidelines
- D-5) PSA application to design, operation and maintenance
- E-1) Others
- E-2) Approaches and methods to compute uncertainty in licensing calculations