Nuclear Thermal Hydraulics

Description

• To be familiarised with various reactor types and their main design and operational characteristics • To learn how to estimate the volumetric heat generation rate in fission reactor cores under normal operation and shutdown conditions • To learn how to analyse the thermal performance of nuclear fuel elements • To learn the basic fluid mechanics of single phase reactor cooling systems • To learn to calculate pressure drop in reactor systems, including tube bundles, and spacer grids • To learn to analyse the heat transfer characteristics of single phase reactor cooling systems • To learn the basic fluid mechanics of two-phase systems, including modelling approaches, flow regime maps, void-quality relations, and pressure drop evaluation • To learn the fundamentals of boiling heat transfer, and its implications for reactor design • To calculate and analyze the coolant conditions throughout a reactor loop including the determination of natural convection regime • To learn the fundamentals of core thermal design, e.g. flow rate/pressure drop relation under different conditions (friction dominated/gravity dominated) for the evaluation of cooling performances