Abstract
The neutral beam injector (NBI) generates a high-energy ion beam and neutralizes it, and then relies on drift transmission to inject the formed neutral beam into the fusion plasma to increase the plasma temperature and drive the plasma current. In order to better cooperate with the Experimental Advanced Superconductive Tokamak (EAST), part of the Chinese major national scientific and technological infrastructure, in carrying out long-pulse high-parameter physics experiments of 400 s and above, this paper considers the optimization of the current design and operation of the NBI beam line with a pulse width of 100 s. Based on an upgraded and optimized NBI vacuum chamber and the structure of the beam-line components, the gas-source characteristics under the layout design of the NBI system are analyzed and an NBI vacuum system that meets relevant needs is designed. Using Molflow software to simulate the transport process of gas molecules in the vacuum chamber, the pressure gradient in the vacuum chamber and the heat-load distribution of the low-temperature condensation surface are obtained. The results show that when the NBI system is dynamically balanced, the pressure of each vacuum chamber section is lower than the set value, thus meeting the performance requirements for the NBI vacuum system and providing a basis for subsequent implementation of the NBI vacuum system upgrade using engineering.
Highlights
In order to realize the high-parameter, steady-state operation of a tokamak nuclear fusion device, the support of a high-power auxiliary heating system is required
Neutral beam injection is one of the main methods used for external heating and maintenance of plasma in tokamak nuclear fusion devices
The performance of the neutral-beam injector (NBI) vacuum system has a great impact on the efficiency of the Neutral beam injection and the service life and safety of related components in the beam line [1,2,3]
Summary
In order to realize the high-parameter, steady-state operation of a tokamak nuclear fusion device, the support of a high-power auxiliary heating system is required. Neutral beam injection is one of the main methods used for external heating and maintenance of plasma in tokamak nuclear fusion devices. It is the auxiliary heating method with the highest heating efficiency and the clearest physical mechanism. The neutral-beam injector (NBI) is an equipment system that implements Neutral beam injection in a fusion device. It generates a high-energy neutral ion beam and relies on drift transmission to inject the formed neutral beam into fusion plasma to increase the plasma temperature and drive the plasma current. The performance of the NBI vacuum system has a great impact on the efficiency of the Neutral beam injection and the service life and safety of related components in the beam line [1,2,3]
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