APPLIED THERMAL HYDRAULICS EXPERIMENT

Description

This course provides experimental programs to cultivate student’s hands-on experience through the lab scale experiments of nuclear thermal hydraulics occurs in the nuclear power plant systems. Measurements of forced convective pressure drop and heat transfer, onset of nucleate boiling, critical heat flux and nucleate boiling heat transfer coefficients, and thermophysical properties of thermal fluid will be performed in the various thermodynamic conditions. Co-run by the Department of Nuclear Engineering at Seoul National University and Kyunghee University, visualization of pool boiling phase change phenomena and single- and multi-phase flow will be experimented to nourish advanced and skilled nuclear engineers who can adapt themselves easily in the related fields of nuclear industry and research.