Thermal Hydraulics
& Reactor Physics

Nuclear Thermal Hydraulics (NTH) is the study of heat transfer and fluid flow in nuclear systems, providing the scientific basis for understanding how heat generated by fission is transported safely and efficiently through the reactor’s coolant. It underpins reactor design and safety by examining phenomena such as convection, pressure drop, and heat transfer under various flow conditions.

Thermal Hydraulic Research and Production Capabilities

At Bangor University, two major facilities advance research in this field: the THOR (Thermal Hydraulics Open-access Research) facility and the BULLET (Bangor University Lead Loop for Erosion/Corrosion Testing) facility. THOR focuses on water-based thermal hydraulics, particularly two-phase flow, boiling, and heat transfer processes relevant to

light-water reactor systems, while BULLET investigates single-phase liquid-lead flow and heat transfer, along with material degradation mechanisms such as corrosion and erosion that occur in heavy liquid metal environments. Together, these facilities enhance the understanding of Nuclear Thermal Hydraulics across different coolant systems and reactor concepts.