Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform
Author:
Affiliation:
1. School of Naval Architecture, Dalian University of Technology, Dalian, China
2. State Key Laboratory of Structural Analysis for Industrial Equipment, Dalian University of Technology, Dalian, China
Funder
Fundamental Research Funds for the Central Universities
National Natural Science Foundation of China
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2023.2290712
Reference22 articles.
1. Chen P, Zhang SC, Zhang YC. Performance analysis of PWR fuel assembly and fuel element. Harbin, China: Harbin Engineering University Press; 2020.
2. Research on the resistance characteristics of rod bundles channels with 5×5 mixing grid;Li Q;Nucl Power Eng,2015
3. Numerical simulation of mixed turbulence in rod bundles channels with lattice;Wei ZL;Nucl Power Eng,2015
4. Verification and validation of CFD and its application in PWR fuel assembly
5. Numerical investigation on mixing performance in rod bundle with spacer grid based on anisotropic turbulent mixing model
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