Coupling thermo-fluid-structure field are analyzed by use of CFD and FEM. A direct simulation of 3D liquid metal flow in the Dual Coolant Lead Lithium (DCLL) blanket is conducted to study the MHD effects and heat transfer influenced by different material properties of FCI (Flow Channel Insert). A consistent and conservative scheme and PISO method on an unstructured collocated mesh are employed to solve the incompressible Navier-Stokes equations with the Lorentz force included based on an electrical Potential formula. The finite element method is employed to study mechanical behavior of FCI. The velocity distribution, MHD pressure drop, current stream lines and temperature distribution of blanket, thermal deformations and thermal stresses in FCI under external magnetic field are investigated. The effects of thickness and electric conductivity of a silicon carbide FCI on temperature field in fluid-structure coupling field, thermal stresses and deformation are analyzed. This work is the theoretical basis of optimizing blanket.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5580-5
PROCEEDINGS PAPER
Simulation of MHD Effects and Thermal Issues in the DCLL Blanket for ITER
Long Chen,
Long Chen
University of Chinese Academy Sciences, Beijing, China
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Yue-Fei Du,
Yue-Fei Du
University of Chinese Academy Sciences, Beijing, China
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Ming-Jiu Ni,
Ming-Jiu Ni
University of Chinese Academy Sciences, Beijing, China
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Nian-Mei Zhang
Nian-Mei Zhang
University of Chinese Academy Sciences, Beijing, China
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Long Chen
University of Chinese Academy Sciences, Beijing, China
Yue-Fei Du
University of Chinese Academy Sciences, Beijing, China
Ming-Jiu Ni
University of Chinese Academy Sciences, Beijing, China
Nian-Mei Zhang
University of Chinese Academy Sciences, Beijing, China
Paper No:
ICONE21-16269, V003T10A038; 7 pages
Published Online:
February 7, 2014
Citation
Chen, L, Du, Y, Ni, M, & Zhang, N. "Simulation of MHD Effects and Thermal Issues in the DCLL Blanket for ITER." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T10A038. ASME. https://doi.org/10.1115/ICONE21-16269
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