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

• Main Author: Rowinski, Marcin Karol
• Other Authors: Zhao Jiyun
• Format: Theses and Dissertations
• Language: English
• Published: 2017
• Subjects: DRNTU::Engineering::Nuclear engineering; DRNTU::Engineering::Mechanical engineering::Fluid mechanics
• Online Access: http://hdl.handle.net/10356/72885
• Institution: Nanyang Technological University

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...