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Preliminary Thermo-hydraulic and Mechanical Analysis for CFETR Divertor

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Abstract

The China Fusion Engineering Test Reactor (CFETR) is a next step tokamak under designing in China, which should be tritium self-sustained by blanket aimed at getting fusion power of 50–200 MW. One of the most challenging components of CFETR is the actively cooled divertor devoted to controlling the plasma boundary, exhausting the heat and reducing the impurities in the plasma. The thermo-hydraulic and mechanical design of the divertor are particularly demanding because of the high heat loads on the divertor plasma-facing components, the critical heat flux, the pressure drop related to the pumping power and the thermal stresses caused by big temperature gradient. In order to verify the feasibility of the divertor cooling structure, finite element calculations have been carried out. The mass rate of the cooling water should be as high as possible concerning the heat loads bearing of the divertor. But simultaneously the pumping power for the cooling system would be higher. In the paper, an optimal mass rate is given as a compromise between the heat loads bearing and the pumping power based on analysis results.

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Acknowledgments

This work is supported by the National Magnetic Confinement Fusion Science Program of China (Grant Nos. 2011GB114003, 2014GB101001 and 2014GB110001) and National Natural Science Foundation of China (Grant No. 11375191).

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Correspondence to Minyou Ye.

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Chen, P., Ye, M., Peng, X. et al. Preliminary Thermo-hydraulic and Mechanical Analysis for CFETR Divertor. J Fusion Energ 34, 901–904 (2015). https://doi.org/10.1007/s10894-015-9892-9

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  • DOI: https://doi.org/10.1007/s10894-015-9892-9

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