Jul 2 – 6, 2018
Žofín Palace
Europe/Prague timezone

P1.1039 Configuration Characteristics of Tokamak-like Stellarator, Chinese First Quasi-axisymmetric Stellarator

Jul 2, 2018, 2:00 PM
2h
Mánes

Mánes

Masarykovo nábřeží 1, 110 00 Praha 1

Speaker

Haifeng Liu

Description

See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P1.1039.pdf Configuration Characteristics of Tokamak-like Stellarator, Chinese First Quasi-axisymmetric Stellarator Haifeng Liu1,4, Akihiro Shimizu2, Mitsutaka Isobe2,3, Shoichi Okamura2, Shin Nishimura2, and Chihiro Suzuki2 Yuhong Xu1, Changjian Tang1,4, Hai Liu1, Xin Zhang1, Bing Liu1, Jie Huang1, Huarong Du1, Xianqu Wang1, Dapeng Yin5, Yi Wan5and CFQS team1,2 1 Institute of Fusion Science, School of Physical Science and Technology, Southwest Jiaotong University, Chengdu 610031, China 2 National Institute for Fusion Science, National Institutes of Natural Sciences, Toki 509-5292, Japan 3 SOKENDAI (The Graduate University for Advanced Studies), Toki 509-5292, Japan 4 Physics Department, Sichuan University, Chengdu 610041, China 5 Hefei Keye Electro Physical Equipment Manufacturing Co., Ltd, Hefei, 230000, China As an internationally collaborative project, the Chinese First Quasi-axisymmetric Stellarator (CFQS) will be fabricated and operated by Southwest Jiaotong University in China and National Institute for Fusion Science in Japan. The CFQS is a tokamak-like stellarator with low-aspect ratio. Via scan of the magnetic configurations with various aspect ratios, major radius and numbers of modular coils, the plasma boundary and modular-coil system for CFQS have been designed and optimized. The candidate parameters of CFQS are as follows: the major radius is 1.0 m, the toroidal magnetic field strength is 1.0 T, the toroidal periodic number is 2 and the aspect ratio is 4.0. The 16 modular coil system has been optimized and designed via minimizing the normal component of magnetic field on the target plasma boundary surface generated from the modular coils, as well as adjusting the main Fourier components of magnetic field strength produced by the modular-coil system to the original ones derived from the target configuration. With these optimized modular coils, VMEC free boundary calculation is conducted to check the beta limit of MHD equilibrium. Mercier stability, ballooning stability and neoclassical transport are calculated to evaluate the property of CFQS configuration. The MHD equilibrium of configuration is almost stable up to beta = 1%. The neoclassical transport in the CFQS is less than that in the W7-X in 1/n regime.

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