Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (6): 60601-060601.doi: 10.11889/j.0253-3219.2020.hjs.43.060601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Study on the transport behavior of fast ions under neutral beam injection heating in EAST

Min XIAO1,2,Bin WU1,Guoqiang ZHONG1(),Liqun HU1,Jinfang WANG1,Baolong HAO1,Juan HUANG1,Ruijie ZHOU1,Kai LI1   

  1. 1.Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China
    2.University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2020-01-14 Revised:2020-02-15 Online:2020-06-15 Published:2020-06-12
  • Contact: Guoqiang ZHONG
  • About author:XIAO Min, male, born in 1990, graduated from University of South China in 2013, doctoral student, focusing on research of fast ion behavior based on neutron diagnostics in tokamak
  • Supported by:
    National Key Research and Development Program of China(2017YFE0300503);National Natural Science Foundation of China(11605241)

Abstract: Background

In order to realize a magnetically confined plasma self-sustaining fusion reaction, fast ions need to be confined in the magnetic field for a long time for them to collide sufficiently, heat the main plasma, and drive the plasma current.


This study aims to explore the fast ions transport behavior of experimental advanced superconducting Tokamak (EAST) neutral beam injection (NBI) heating under different plasma currents and toroidal magnetic field.


The plasma transport analysis code TRANSP and particle-guided center orbit simulation code ORBIT were combined with fusion neutron and plasma stored energy diagnostic data to study the transport behavior of fast ions. Experimental data under different plasma current and toroidal magnetic field intensity were compared with the simulation results.


Experimental and simulation results show that the prompt loss power of fast ions from the neutral beam injection (NBI) counter-beam is higher than that from the NBI co-beam. Under the effect of the clockwise plasma current and the counterclockwise toroidal magnetic field, the loss areas of fast ions prompt loss from the four beam lines of NBI are mainly concentrated in the first wall below midplane and divertor area of the device. Within the current operating parameters of EAST, increasing the plasma current and toroidal magnetic field can reduce the drift orbit width and the larmor radius of fast ions in the plasma, which is much better for the confinement of the fast ions.


Increasing the plasma current and toroidal magnetic field can improve the heating efficiency of the NBI, especially for the counter-beam, which can increase the fusion neutron yield and stored energy of plasma.

Key words: Fast ion behavior, Fusion neutron, Prompt loss, Neutral beam injection, EAST

CLC Number: 

  • TL61,TL65