Unsteady thermal analysis of gas-cooled fast reactor - by Issam Adnan Lakkis
Abstract
This thesis presents numerical analysis of transient heat transfer in an equivalent coolant - fuel rod cell of a typical gas cooled, fast nuclear reactor core. The transient performance is assumed to follow a complete sudden loss of coolant starting from
Description
Thesis (M.E.)-- American University of Beirut. Department of Mechanical Engineering, 1993.;"Advisor: Fadl Moukalled , Associate Professor, Mechanical Engineering -- Members of Committee: Rida Nuwayhid Assistant Professor, Mechanical Engineering Nesrccn
Bibliography: leaves 242.
Bibliography: leaves 242.