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| dc.contributor.author | Lakkis, Issam Adnan |
| dc.date.accessioned | 2012-06-13T06:41:47Z |
| dc.date.available | 2012-06-13T06:41:47Z |
| dc.date.issued | 1993 |
| dc.identifier.uri | http://hdl.handle.net/10938/4802 |
| dc.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 |
| dc.description | Bibliography: leaves 242. |
| dc.description.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 |
| dc.format.extent | xiii, 242 leaves : ill. cm. |
| dc.language.iso | eng |
| dc.relation.ispartof | Theses, Dissertations, and Projects |
| dc.subject.classification | ET:003553 AUBNO |
| dc.subject.lcsh | Fast reactors. |
| dc.subject.lcsh | Nuclear reactors. |
| dc.subject.lcsh | Thermal analysis. |
| dc.title | Unsteady thermal analysis of gas-cooled fast reactor - by Issam Adnan Lakkis |
| dc.title.alternative | Unsteady analysis |
| dc.type | Thesis |
| dc.contributor.department | American University of Beirut. Faculty of Engineering and Architecture. Department of Mechanical Engineering |
