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Engineering Analysis for Vacuum Vessel of CFQS Quasi-Axisymmetric Stellarator

Sho NAKAGAWA¹⁾, Takanori MURASE¹⁾, Akihiro SHIMIZU^1,3), Shigeyoshi KINOSHITA¹⁾, Mitsutaka ISOBE^1,3), Shoichi OKAMURA¹⁾, Yuhong XU²⁾, Haifeng LIU²⁾, Guozhen XIONG²⁾, Hai LIU²⁾, Dapeng YIN⁴⁾, Yi WAN⁴⁾ and CFQS team^1,2,3,4)

1)

National Institute for Fusion Science, National Institutes of Natural Sciences, Toki 509-5292, Japan

2)

Institute of Fusion Science, School of Physical Science and Technology, Southwest Jiaotong University, Chengdu 610031, People's Republic of China

3)

The Graduate University for Advanced Studies, SOKENDAI, Toki 509-5292, Japan

4)

Hefei Keye Electro Physical Equipment Manufacturing Co., Ltd, Hefei 230000, People's Republic of China

(Received 8 January 2020 / Accepted 18 July 2020 / Published 19 August 2020)

Abstract

The world's first quasi-axisymmetric stellarator CFQS (China First Quasi-axisymmetric Stellarator) will be constructed as the joint project of National Institute for Fusion Science (NIFS) in Japan and Southwest Jiaotong University (SWJTU) in China [1]. Physics design of CFQS plasma was completed [2, 3], and numerous efforts are now being made to finalize engineering design of CFQS [4]. The CFQS vacuum vessel (VV) will be made of thin plates of SUS316L with thickness of 6 mm. The thickness is determined by considering fabricability and manufacturing cost. In this report, analyses have been performed to confirm the structural reliability of VV and evaluate the influence of eddy current using finite element method software ANSYS/Mechanical^TM and ANSYS/Maxwell^TM.

Copyright (c) 2020 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

CFQS, quasi-axisymmetric stellarator, vacuum vessel, eddy current, finite element method

DOI: 10.1585/pfr.15.2405066

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References

• [1] M. Isobe et al., Plasma Fusion Res. 14, 3402074 (2019).
• [2] H. Liu et al., Plasma Fusion Res. 13, 3405067 (2018).
• [3] A. Shimizu et al., Plasma Fusion Res. 13, 3403123 (2018).
• [4] S. Kinoshita et al., Plasma Fusion Res. 14, 3405097 (2019).
• [5] S. Okamura, K. Matsuoka et al., Nucl. Fusion 41, 1865 (2001).
• [6] ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components (2010).