Computational fluid dynamics of advanced nuclear reactor cores and its contribution to safety analysis

Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of advanced nuclear reactors. Thermal and pressure drop evaluations of an innovative annular fuel in the European lead-cooled System ELSY fast reactor were conducted. Annular fuel has superior cooling capac...

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Bibliographic Details
Main Author: Rowinski, Marcin Karol
Other Authors: Zhao Jiyun
Format: Thesis
Language:English
Published: 2017
Subjects:
Online Access:http://hdl.handle.net/10356/72885