Thermal-hydraulic analysis of the CFETR TF coils when subject to nuclear heat load

• Published in: Fusion engineering and design Vol. 173; p. 112850
• Main Authors: Wen, Xinghao, Li, Junjun, Sang, Aiguo, Ren, Yong, Liu, Xiaogang, Wu, Yu, Gao, Xiang
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.12.2021; Elsevier Science Ltd
• Subjects: CFETR; Coils (windings); Engineering test reactors; Hydraulics; Mass flow rate; Nuclear fusion; Nuclear heat; Nuclear heat load; Nuclear power plants; Superconducting magnet; Superconducting magnets; Thermal-hydraulic; CFETR; Superconducting magnet; Nuclear heat load; Thermal-hydraulic
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2021.112850

•The Gandalf code is coupled with ANSYS model to analyze the TF coil.•Two possible strategies are investigated to increase the temperature margin of TF coil.•The proposed reduction of hydraulic length is more effective to increase the temperature margin of TF coil. China Fusion Engineering Test Reactor (CFETR) has received much attention over the past several years, aiming at bridging the gap between the International Thermonuclear Experimental Reactor (ITER) and the Demonstration Fusion Reactor (DEMO). The toroidal field (TF) coils play an important role in the tokamak, which provide the main magnetic field to confine the plasma. In order to evaluate the feasibility of superconducting magnets used in CFETR, it is important to predict the magnet performance in terms of temperature margin during normal operation conditions. The simulations confirm the need to increase the mass flow rate, or decrease the hydraulic length of high field windings. The results show that the proposed reduction of hydraulic length is more effective to increase the minimum temperature margin.