أنتقال الحرارة في الهندسة النووية (المفاعلات النووية) لطلاب الدراسات العليا

Fundamentals of heat transfer mechanisms, reactor heat generation and transfer; radial and axial temperature distributions in fuel elements, applications of single-phase, two-phase flow and convective boiling to reactor coolant channel analysis, core thermal design and safety analysis, two-phase flow patterns, critical heat flux, void coefficient, radiative heat transfer, thermal hydraulic safety limits and conditions, current research topics of the nuclear thermal hydraulics concerned with safe and effective heat removal from the reactor core for power production. Analysis of operational and accident transient sequences, nuclear and thermal-hydraulic transient, and engineering aspects of nuclear reactor safety.