CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR

Yingjie Wang; Mingjun Wang; Haoran Ju; Minfu Zhao; Dalin Zhang; Wenxi Tian; Tiancai Liu; Suizheng Qiu; G.H. Su

Nuclear Engineering and Technology (Jul 2020)

CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR

Yingjie Wang,
Mingjun Wang,
Haoran Ju,
Minfu Zhao,
Dalin Zhang,
Wenxi Tian,
Tiancai Liu,
Suizheng Qiu,
G.H. Su

Affiliations

Yingjie Wang: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Mingjun Wang: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.
Haoran Ju: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Minfu Zhao: China Institute of Atomic Energy, P. O. Box 275-59, Beijing, 102413, China
Dalin Zhang: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.
Wenxi Tian: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Tiancai Liu: China Institute of Atomic Energy, P. O. Box 275-59, Beijing, 102413, China
Suizheng Qiu: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
G.H. Su: School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China

Journal volume & issue: Vol. 52, no. 7
pp. 1386 – 1395

Abstract

Read online

High fidelity nuclear reactor fuel assembly simulation using CFD method is an effective way for the structure design and optimization. The validated models and user practice guidelines play critical roles in achieving reliable results in CFD simulations. In this paper, the international benchmark MATiS-H is studied carefully and the best user practice guideline is achieved for the rod bundles simulation. Then a 5 × 5 rod bundles model in the advanced pressurized water reactor (PWR) is established and the detailed three-dimensional thermal-hydraulic characteristics are investigated. The influence of spacer grids and mixing vanes on the flow and hear transfer in rod bundles is revealed. As the coolant flows through the spacer grids and mixing vanes in the rod bundles, the drastic lateral flow would be induced and the pressure drop increases significantly. In addition, the heat transfer is enhanced remarkably due to the strong mixing effects. The calculation results could provide meaningful guidelines for the design of advanced PWR fuel assembly.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

About the journal

Abstract

Keywords