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Science and Technology of Nuclear Installations
Volume 2015, Article ID 198654, 13 pages
Research Article

Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor

1Department of Engineering Physics, Tsinghua University, Beijing 100086, China
2Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, China

Received 9 January 2015; Revised 2 April 2015; Accepted 16 April 2015

Academic Editor: Hyung-Jin Shim

Copyright © 2015 Daxin Gong et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard and control fuel assemblies. The simulation is carried out with an inlet coolant velocity varying from 4.5 m/s to 7.5 m/s in hot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated ranges. The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly. Additionally, the assembly with a hot spot is specially studied, and the safety of the research reactor is also approved.