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Unsteady thermal analysis of gas-cooled fast reactor - by Issam Adnan Lakkis

Unsteady thermal analysis of gas-cooled fast reactor - by Issam Adnan Lakkis

Lakkis, Issam Adnan
URI: http://hdl.handle.net/10938/4802
Date: 1993

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.
 

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