CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR-Reference-Cited by-同舟云学术

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

Published:2020-07 Issue:7 Volume:52 Page:1386-1395
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

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

Funder

National Key R&D Program of China

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. Heat transfer near spacer grids in gas-cooled rod bundles;Hassan;Nucl. Technol.,1981

2. An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle;Shen;Nucl. Eng. Des.,1991

3. Spacer grid effects on turbulent flow in rod bundles;Yang;Journal of the Korean Nuclear Society,1996

4. Experimental investigation of turbulent flow through spacer grids in fuel rod bundles;Caraghiaur;Nucl. Eng. Des.,2009

5. Mapping of the lateral flow field in typical subchannels of a support grid with vanes;McClusky;Journal of Fluids Egineering,2003

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2. Pressurized water reactor fuel corrosion-related unidentified deposit and its related safety issues – III. N-TH-M coupled CIPS prediction;Annals of Nuclear Energy;2024-12

3. The numerical investigation of the thermal–hydraulic behavior in a 3 × 3 rod bundle with spacer grids;Annals of Nuclear Energy;2024-12

4. Rapid predictions of pressure and velocity fields in a 5 × 5 bending fuel assembly based on a POD-based black-box model;Annals of Nuclear Energy;2024-11

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