15–19 Nov 2021
Fukuoka Convention Center
Asia/Tokyo timezone

Thermal Analysis of Toroidal Field Coil of EAST During Plasma Discharges

THU-PO3-206-12
18 Nov 2021, 10:00
2h
Fukuoka Convention Center

Fukuoka Convention Center

Speaker

Xinghao Wen (University of Science and Technology of China)

Description

Abstract-Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak in the world. The superconducting magnets are made of NbTi Cable-In-Conduit Conductor (CICC). The heat load due to plasma discharge rises the temperature of magnet. If the cooling of magnet is not sufficient and the temperature margin of the superconductive cables is not enough, it maybe induce the magnet quenches. In order to safe operation of EAST with higher plasma performance discharge in future, it is important to estimate the operation state of TF magnet. It is found that the outlet temperature rise of TF windings and cases is nearly proportional to plasma current, and the outlet temperature rise of TF windings is not related to the plasma duration, whereas the outlet temperature rise of TF cases seems to increase with plasma duration according to the experimental results.
In order to further study the relationship between the parameters of plasma discharge and the temperature rise of TF windings and cases, the SAITOKPF code is used to analyze the experimental phenomenon.

Index Term- EAST, toroidal field, plasma discharge, temperature margin

Acknowledgments: This work was supported in part by the National Natural Science Foundation of China under Grant No. 51777207.

Primary authors

Xinghao Wen (University of Science and Technology of China) Jun jun Li (Institute of Plasma Physics, Chinese Academy of Sciences) Aiguo Sang (Institute of Plasma Physics, Chinese Academy of Sciences)

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