Concept Design of CFETR Tokamak Machine
@article{Song2014ConceptDO, title={Concept Design of CFETR Tokamak Machine}, author={Y. Song and S. Wu and J. Li and B. Wan and Y. X. Wan and P. Fu and M. Y. Ye and J. X. Zheng and K. Lu and X. Gao and Su Mei Liu and X. F. Liu and M. Z. Lei and X. B. Peng and Y. Chen}, journal={IEEE Transactions on Plasma Science}, year={2014}, volume={42}, pages={503-509} }
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… CONTINUE READING
Figures, Tables, and Topics from this paper
206 Citations
Concept design of CFETR Tokamak machine
- Engineering
- 2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
- 2013
- 16
Overview of the Design Status of the Superconducting Magnet System of the CFETR
- Physics
- IEEE Transactions on Applied Superconductivity
- 2018
- 12
Conceptual Design of the CFETR Toroidal Field Superconducting Coils
- Physics
- IEEE Transactions on Applied Superconductivity
- 2015
- 16
Electromagnetic Design and Challenges for 14 T High-Tc Toroidal Field Superconducting Magnet for CFETR
- Physics
- IEEE Transactions on Applied Superconductivity
- 2019
- 3
Conceptual design and analysis of CFETR magnets
- Engineering
- 2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
- 2013
- 12
Feasibility Analysis of 100 kA DC Commutation Scheme to be Applied in the Quench Protection Unit of CFETR
- Physics
- IEEE Transactions on Applied Superconductivity
- 2020
- 4
References
SHOWING 1-10 OF 16 REFERENCES
Concept design of CFETR Tokamak machine
- Engineering
- 2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
- 2013
- 16
Concept design of CFETR superconducting magnet system based on different maintenance ports
- Physics
- 2013
- 54
Structural analysis and manufacture for the vacuum vessel of experimental advanced superconducting tokamak (EAST) device
- Materials Science
- 2006
- 16
Design of the HT-7U tokamak device
- Physics
- 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050)
- 1999
- 12
Overview of steady state operation of HT-7 and present status of the HT-7U project
- Materials Science
- 2000
- 173
The European contribution to the procurement of the ITER Remote Handling systems
- Computer Science
- 2009
- 8