Preliminary CFD and EM analysis of the ECRH equatorial launcher port plug prototype towards the CFETR

被引:0
作者
Li, Dingzhen [1 ,2 ]
Tang, Yunying [1 ]
Zhang, Chao [3 ]
Wang, Hanlin [1 ,2 ]
Zhang, Liyuan [1 ,2 ]
Zhou, Nengtao [1 ]
Wang, Yuehang [1 ]
Wang, Xiaojie [1 ]
Liu, Fukun [1 ]
机构
[1] Chinese Acad Sci, Hefei Inst Phys Sci, Inistitute Plasma Phys, Hefei 230031, Peoples R China
[2] Univ Sci & Technol China, Hefei 230026, Peoples R China
[3] Shenzhen Univ, Shenzhen 518052, Guangdong, Peoples R China
关键词
CFETR; ECRH; Port plug; EM; FINAL DESIGN; ITER;
D O I
10.1016/j.nme.2023.101554
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The CFETR is the next generation magnetic confinement tokamak, its increasing heating needs and stringent shielding requirements present new challenges for the ECRH launcher. In an effort to evaluate the viability of the equatorial launcher, a port plug prototype is designed and its performance under steady state or some interrupted events is assessed. The well-configured steel/water ratio is beneficial to improve its shielding capability and effectively mitigate the 493 kW heat. The maximum temperature of the port plug is less than 300 degrees C when the inlet temperature is 70 degrees C, and the average outlet water temperature reaches 142 degrees C. The worst EM case is a major disruption of the plasma, which would induce about 200 kN force on the port plug at the end of the plasma current linear decay. The combined heat and EM force loads on the port plug would result in a total deformation of 1.7 mm and a maximum equivalent stress of 320 MPa, with little impacts on the port plug or the surrounding vacuum vessel. As the installation of the port plug, the H and He generation rates of the surrounding vacuum vessel have increased by about 2 % and 1 % separately, but remain lower than the limit of 1 appm/FPY, and the nuclear heat density of the toroidal field coils has increased by about 5%.
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页数:13
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