Thermal–hydraulic performance of a 5 × 5 rod bundle with spacer grid in a nuclear reactor-Reference-Cited by-同舟云学术

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Thermal–hydraulic performance of a 5 × 5 rod bundle with spacer grid in a nuclear reactor

Published:2016-06 Issue: Volume:103 Page:1416-1426
ISSN:1359-4311
Container-title:Applied Thermal Engineering
language:en
Short-container-title:Applied Thermal Engineering

Author:

Chen Deqi,Xiao Yi,Xie Shijie,Yuan Dewen,Lang Xuemei,Yang Zile,Zhong Yunke,Lu Qi

Funder

National Natural Science Foundation of China

Chongqing Natural Science Foundation

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Energy Engineering and Power Technology

Reference22 articles.

1. A numerical prediction on the turbulent flow in closely spaced bare rod arrays by a nonlinear k–ε model;Kye;Nucl. Eng. Des.,1997

2. A turbulence model study for simulating flow inside tight lattice rod bundles;Baglietto;Nucl. Eng. Des.,2005

3. CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly;Liu;Appl. Therm. Eng.,2012

4. Turbulent flow through spacer grids in rod bundles;Yang;J. Fluids Eng.,1998

5. Fully developed combined convection in a seven-rod horizontal bundle;Haldar;Int. J. Heat Mass Transf.,2000

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1. 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

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

3. Numerical study on the size effect on the mixing in 2×1, 3×3 and 5×5 rod bundle subchannels;Nuclear Engineering and Technology;2024-07

4. Flow fields prediction for data-driven model of 5 × 5 fuel rod bundles based on POD-RBFNN surrogate model;Nuclear Engineering and Design;2024-06

5. The reduced-order model of 5 × 5 fuel rod bundles;Physics of Fluids;2024-04-01

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