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# 28th IAEA Fusion Energy Conference (FEC 2020)

May 10 – 15, 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

## New Compact Torus Injection System on KTX reversed field pinch device

May 13, 2021, 8:30 AM
4h
Virtual Event

#### Virtual Event

Regular Poster Fusion Energy Technology

Chen Chen

### Description

The compact torus (CT) plasma is a self-organized plasmoid used for fuelling and providing external helicity and momentum. Recent research has shown that central fuelling greatly improves the tritium breeding ratio, which is a key parameter in tritium fusion devices [1]. As the most promising fuelling solution for future fusion devices, such as ITER and CFETR, CT plasma can achieve an ultra-high velocity of over 100 km/s to penetrate a strong magnetic field with magnetic reconnection processes to realize central fuelling. The main requirement for CT penetration is governed by the empirical condition: $\frac{1}{2}\rho_{ct}\nu^2_{ct}>{B^2}/{2\mu_0}$, which the physical image shows the initial directional kinetic energy density of CT plasma must be higher than the magnetic energy density at the penetration position [2].
A new compact torus injector (KTX-CTI) has been developed on Keda Torus eXperiment (KTX) [3], which is a medium size reversed field pinch (RFP) device. The three-meter long coaxial injector, shown in Fig. 1(http://staff.ustc.edu.cn/~lantao/Fig.1.jpg), is designed to inject CT plasmoid into KTX. In the engineering commissioning, the maximum injection mass of CT is over 50 $\mu$g for hydrogen, which is about 30% of the KTX plasma particle inventory, and the electron density of CT can reach $10^{22}\ \rm{m}^{-3}$. The CT plasma can be accelerated to a directional speed higher than $100\ \rm{km/s}$ though strong $\bf J\times B$ force. At the same time, KTX-CTI is equipped with various in-situ and compact diagnostics for the operation and physics research such as optical fiber interferometer, spectrometer, Rogowski coil, magnetic field probe and Langmuir probe array.
After the commissioning, KTX-CTI is installed to KTX in the middle plane. Since the maximum toroidal magnetic field of KTX is about 0.2 T, a CT plasmoid with electron density greater than $3\times 10^{21}\ \rm{m}^{-3}$ and a velocity above $80\ \rm{km/s}$ can easily reach the central region of KTX. The penetration position will be directly viewed from the H$\alpha$ array in the top diagnostic port of KTX. The injection angle can be adjusted from 0$^\circ$ to 25$^\circ$ with respect to the major radius direction at the CT entry location in the middle plane shown in Fig.2 (http://staff.ustc.edu.cn/~lantao/Fig.2.jpg). When the injection angle is set to a none-zero angle, the CT will introduce a net tangential momentum, and it is possible to induce and sustain toroidal rotation of the KTX plasma due to external momentum transfer from the CT to KTX plasma bulk. In addition, a small amount of helicity carried by rolling CT can also be introduced to KTX plasma.
It is the first time that the CT plasma is injected into a RFP device, and it is significant to study the interaction between CT and RFP, especially the impact of CT on RFP confinement. Just as the confinement was improved through CT injection in the tokamak experiments [4,5], it is expected to be successful in the confinement research of RFP, especially in the single helicity mode (SH) research. In advance, KTX-CTI will become a pre-research platform to test the high-frequency and long-distance injection, including the injector machine and power supply, for future fusion device such as ITER and CFETR.
This work was supported by the National Magnetic Confinement Fusion Science Program of China (under grant nos. 2017YFE0301700 and 2017YFE0301701) and the Natural Science Foundation of China (under grant nos. 11875255, 11635008, 11375188 and 11975231).

References:
[1] G. Zhuang et al., Progress of the CFETR design, Nucl. Fusion 59 112010 (2019).
[2] P.B. Parks, Refueling Tokamaks by Injection of Compact Toroids, Phys. Rev. Lett. 61 1364 (1988).
[3] W. Liu et al., An overview of diagnostic upgrade and experimental progress in the KTX, Nucl. Fusion 59 112013 (2019).
[4] C. Xiao et al. Tangential and Vertical Compact Torus Injection Experiments on the STOR-M Tokamak, Plasma Sci. Technol. 7 2701 (2005).
[5] M. Nagata et al. Experimental studies of the dynamics of compact toroid injected into the JFT-2M tokamak, Nucl. Fusion 45 1056 (2005).

Country or International Organization China University of Science and Technology of China

### Co-authors

Tao Lan (University of Science and Technology of China) Ge Zhuang (Huazhong University of Science and Technology) Defeng Kong (Institute of Plasma Physics, Chinese Academy of Sciences) Mr Shoubiao Zhang (Institute of Plasma Physics, Chinese Academy of Sciences) YUNTAO SONG (Institute of Plasma Physics, Chinese Academy of Sciences) Jiangang Li (Institute of Plasma Physics, Chinese Academy of Sciences) Dr Sen Zhang (University of Science and Technology of China) Dr Jie Wu (University of Science and Technology of China) Dr Tijian Deng (University of Science and Technology of China) Dr Junfeng Zhu (University of Science and Technology of China) Yi Yu (CnUSTC) Prof. Zhengwei Wu (University of Science and Technology of China) wenzhe mao (University of Science and Technology of China) Prof. Ahdi Liu (University of Science and Technology of China) Prof. Jinlin Xie (University of Science and Technology of China) Prof. Hong Li (University of Science and Technology of China) Weixing Ding (UCLA) Chijin Xiao (University of Saskatchewan) Wandong Liu (University of Science and Technology of China)

### Presentation materials

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