Progress of the CFETR design

TLDR

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. The CFETR aims to demonstrate up to 200 MW fusion power initially, reach 1 GW, achieve a duty factor of 0.3–0.5, and attain tritium self‑sufficiency (TBR > 1), while outlining R&D activities, neutral‑beam and wave‑driven current drive schemes, and engineering design of key systems. A physics‑based multi‑dimensional code suite was used to develop steady‑state and hybrid scenarios at up to 6.5 T, and the design incorporates negative‑ion neutral beam injection, high‑frequency electron cyclotron, lower hybrid, and fast waves for current drive, along with detailed engineering of magnets, vacuum, tritium breeding blanket, divertor, and remote handling systems.

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.