Progress of the CFETR design. (5th June 2019)

• Record Type: Journal Article
• Authors: Zhuang, G.; Li, G.Q.; Li, J.; Wan, Y.X.; Liu, Y.; Wang, X.L.; Song, Y.T.; Chan, V.; Yang, Q.W.; Wan, B.N.; Duan, X.R.; Fu, P.; Xiao, B.J.
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 59:Number 11(2019:Nov.)
• Publication Date: 2019-06-05
• Subjects: CFETR -- tritium self-sufficiency -- steady-state operation -- fusion reactor design; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/ab0e27
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to eventually reach DEMO relevant power level 1 GW, to manifest a high duty factor of 0.3–0.5, and to pursue tritium self-sufficiency with tritium breeding ratio (TBR) >1. The key challenge to meet the missions of the CFETR is to run the machine in steady state (or long pulse) and high duty factor. By using a multi-dimensional code suite with physics-based models, self-consistent steady-state and hybrid mode scenarios for CFETR have been developed under a high magnetic field up to 6.5 T. The negative-ion neutral beam injection together with high frequency electron cyclotron wave and lower hybrid wave (and/or fast wave) are proposed to be used to drive the current. Subsequently the engineering design of CFETR including the magnet system, vacuum system, tritium breeding blanket, divertor, remote handling and maintenance system will be introduced. Some research and development (R&D) activities are also introduced in this paper.