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Fusion
Published in William J. Nuttall, Nuclear Renaissance, 2022
A key step in China’s journey was signing up to join the ITER project in 2003 [66]. At that time, the ITER project needed more international financial support. The monetary cost to China was substantial but the price allowed China to fully join the global fusion club. On 23 January 2003, Nature magazine reported that China’s Minister of Science, Xu Gusnhua, had announced, ‘China intends to make a major contribution to the project in the form of material or funding’ [67]. Over the years, the domestic Chinese fusion programme proceeded in parallel with the slow development of the massive ITER device. In December 2020 the former HL-2A tokamak, now fully upgraded as HL-2M, was turned on in Chengdu, Sichuan province [68]. China has a 2015 roadmap for the way ahead and prominent in that is a planned China Fusion Engineering Test Reactor to be developed in the 2020s as a tangible step towards testing and demonstrating fusion power engineering and technology [69].
Progress of Engineering Design of CFETR Machine Assembly
Published in Fusion Science and Technology, 2022
Lijun Cai, Kun Lu, Yong Lu, Chunlin Lai, Junsong Shen, Dequan Liu, Jianghua Wei, Jian Liu, Yongqi Gu, Tao Lin, Mingxuan Lu, Yuxiang Liu
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak reactor under design in China based on the physical and technical achievements of HL-2A/2M, EAST, and the International Thermonuclear Experimental Reactor (ITER) and aimed at exploring the key technical solutions for licensing DEMOnstration nuclear fusion reactor (DEMO) fusion power plants.1–3 The major radius of CFETR is 7.2 m, and its minor radius is 2.2 m. The maximum CFETR fusion power reaches 1500 MW, which is much higher than that of ITER. In addition, one of the important differences between CFETR and ITER is that the former will realize self-sustaining plasma burning (e.g., a duty cycle of 0.3 to 0.5, fusion power gain Q > 10, and the requirement of ~50 displacements per atom), which would greatly promote the application of fusion energy.4,5
Preliminary Safety Analysis of Tritium Source Term for the CFETR Tritium Plant
Published in Fusion Science and Technology, 2020
Shiping Wei, Xinyu Sun, Haixia Wang, Jiangtao Jia, Zhibin Chen, Shichao Zhang
The China Fusion Engineering Test Reactor (CFETR) is the next-generation device of Chinese magnetic confinement fusion, which has an ambition to bridge the gaps mainly in tritium self-sufficiency and electricity production between ITER and the demonstration reactor DEMO. The CFETR conceptual design has been accomplished by domestic and international cooperation and efforts.1 The CFETR has a higher amount of tritium inventory than ITER, and its maximum tritium inventory would be about 6 kg (Refs. 2 and 3). Due to a small burnup fraction (maximum 5%) in the vacuum vessel2 (VV), most of the unburned plasma gas–mixed tritium should be possessed and recycled in the CFETR tritium plant. However, tritium is one of the most mobile radioactive source terms present in fusion reactors and has the potential to release to the environment. Thus, tritium management becomes a big challenge for the CFETR tritium plant. The quantification of the tritium source term is one important issue for tritium management, safety assessment, and operation of the CFETR in the first place, and then to set up models to obtain information about tritium streams and to predict the environmental release during the evolution of normal and accidental scenarios.4 The tritium source term is also used in dose or health-effect calculations.
Quench Detection Design for CFETR CSMC
Published in Fusion Science and Technology, 2018
Teng Wang, Yanlan Hu, Huajun Liu, Yu Wu, Yi Shi, Chao Pan, Longgui Zheng
The China Fusion Engineering Test Reactor (CFETR) is the Chinese next-generation tokamak device whose objective is to design and build a tokamak experimental reactor before the construction of fusion power station. The CFETR Central Solenoid Model Coils (CSMC) program has been carried out since 2014 as one of the largest research and development (R&D) programs in the CFETR Engineering Design Activity designed by China independently. The CSMC project has the same scientific objectives and physical parameters as the central solenoid (CS) coils on CFETR, namely The maximum magnet field is 12 T.The maximum magnetic field change rate is 1.5 T/s.The objective is to prevent the degradation of magnet performance in case of operational events like the quench of magnet superconductors.