Concept design of CFETR tokamak machine
Abstract
China Fusion Engineering Test Reactor (CFETR) is a tokamak reactor; one design option under the consideration of the China National Integration Design Group employs superconducting magnets. The fusion power is at the range of 50–200 MW and the duty cycle (or burning time) was envisioned as 30%–50%. The plasma current will be 10 MA and the major and minor radii are 5.7 and 1.6 m, respectively. The concept engineering design including the magnet system, vacuum vessel (VV) system, and maintenance method has been carried out in the past years. The toroidal magnetic field strength at$R_{0}$is 5 T and the maximum flux swing provided by central solenoid winding will be 160 VS. The main design work, including the electromagnetic analysis of the magnet system, has already been carried out. This paper mainly probes into the VV design and optimization based on three types of maintenance ports. Furthermore, the maintenance method, counted as one of the most important design studies, is presented specifically in this paper. It includes the design of the maintenance ports and the remote handling system design, and so on. The next design stage will mainly include mechanical design, conductor stability, different types of divertor system design, and so on.
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China, the EU, and Japan have carried out studies on DEMO, and the engineering design of the Chinese Fusion Engineering Testing Reactor was completed in 2021.
“China,82 the EU,83 and Japan84 have carried out their studies on DEMO, and the engineering design of the Chinese Fusion Engineering Testing Reactor was completed in 2021.”
From Technologies and perspectives for achieving carbon neutrality (2021) · cites this paper as [82]
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Technologies and perspectives for achieving carbon neutrality
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- Authors
- Song, Y. T., Wu, S. T., Li, J. G., Wan, B. N., Wan, Y. X., Fu, P., Ye, M. Y., Zheng, J. X., Lu, K., Gao, X., Liu, S. M., Liu, X. F., Lei, M. Z., Peng, X. B., & Chen, Y.
- Affiliations
- University of Science and Technology of China (CN)
- Chinese Academy of Sciences (CN)
- Venue
- IEEE Transactions on Plasma Science
- Published
- 2014-03
- Volume
- 42
- Issue
- 3
- Pages
- 503-509
- ISSN
- 0093-3813 (ISSN-L)
- 1939-9375
- OpenAlex
- W2128350346
- Cited by
- 374
- References
- 11
- Citations by year
- 2026: 14 · 2025: 17 · 2024: 25 · 2023: 30 · 2022: 43 · 2021: 40 · 2020: 46 · 2019: 25 · 2018: 47 · 2017: 37 · 2016: 23 · 2015: 19 · 2014: 5 · 2013: 3
- FWCI
- 12.34
- Type
- journal article
- Language
- en
- Open access
- closed
- Locations
- IEEE Transactions on Plasma Science (publishedVersion)
- Topics
- Physical Sciences › Physics and Astronomy › Nuclear and High Energy Physics › Magnetic confinement fusion research
- Physical Sciences › Engineering › Biomedical Engineering › Superconducting Materials and Applications
- Physical Sciences › Materials Science › Materials Chemistry › Fusion materials and technologies
- Keywords
- CFETR, tokamak reactor, vacuum vessel design, remote handling system, superconducting magnets, electromagnetic analysis, toroidal magnetic field, central solenoid, fusion reactor maintenance
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