This workshop offers a comprehensive journey through the critical interaction between experimental research and computational modelling in the fields of thermal hydraulics and fluid dynamics, which support key technologies across energy, aerospace, and environmental sectors, particularly in the context of nuclear reactor systems, where accurate modelling is essential for safety, performance, and innovation.

Participants will explore how experimental studies lay the groundwork for theoretical development, inform numerical modelling, and guide the implementation and verification of computer codes. The workshop will delve into the validation process that ensures these models can be reliably applied to real-world systems.

Through selected case studies, the workshop will demonstrate how bridging experimental insights with computational tools has led to transformative advancements. The sessions will progress from single-phase heat transfer to more complex two-phase heat and mass transfer phenomena, with special emphasis on challenging two-phase flow behaviours encountered in nuclear applications.

• Basic understanding of heat transfer, fluid mechanics, and thermodynamics.
• Familiarity with single-phase and two-phase flow concepts.
• Basic understanding of computational modelling, including system analysis and CFD methodologies.

By the end of the workshop, participants will:

• Understand the fundamental role of experimental studies in developing and validating thermal-hydraulic and fluid-dynamic models.
• Recognise the process of bridging experimental data to computational modelling, including model development, verification, and validation.
• Evaluate the limitations and applicability of computational results based on experimental validation.
• Gain familiarity with the key challenges in simulating single-phase and two-phase flow and heat transfer, especially in nuclear reactor systems.

• Background / Introduction
• Single-phase convective heat transfer
• Two-Phase Flow thermal hydraulics
• Rod Bundle Flow behavior
• Rod Bundle Heat Transfer (RBHT)
• Large-scale integral testing facilities
• Particle transport
• Simulations toward applications
• Conclusions