Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method

Author:

Li Xiangyu1,Wang Guanghuai2,Guo Yun1,Li Songwei3

Affiliation:

1. School of Nuclear science, University of Science and Technology of China, Hefei, China

2. China Ship Development and Design Center, Wuhan, China

3. State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, China

Abstract

Situated at the bottom of the vacuum vessel, the divertor extracts heat and ash produced by the fusion reaction, minimizes plasma contamination, and protects the surrounding walls from thermal and neutronic loads. The vertical targets of divertor are designed to be able for up to 20 MW/m2 high heat flux. It is a great ordeal for both the material performance and the cooling ability. Critical heat flux (CHF) margin is very crucial during the design of divertor. ANSYS FLUENT is used in this paper to predict the CHF on a monoblock structure with a twisted tape inside the tube. Numerical results are validated with the corresponding sets of experimental results. In this paper, CFD method used to predict CHF of divertor cooling channel was first introduced. On the other hand, influence of inlet subcooling on CHF is studied in detail. The inlet subcooling affect the CHF much complicated for the single- side heated and swirl flow channel. Whether the influencing trend or the locations of CHF occurrence are different under different inlet subcooling. The derivations between the simulation and experimental results were no more than 32%. This study proves the CFD tools can provide efficient help on the understanding of the CHF phenomenon of complex construction.

Publisher

National Library of Serbia

Subject

Renewable Energy, Sustainability and the Environment

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