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1·In fusion research, the neutral beam injection has become an efficient method for heating plasma.

在受控核聚变研究中，中性束注入已经成为加热等离子体的有效手段。

2·This paper introduces a fast turn off power protector for HL 1m neutral beam injector power supply system.

介绍了用于HL1M中性束注入器电源系统中的一个快速断电保护器。

3·Neutral beam injection (NBI) heating is one of the main auxiliary heating methods in controllable nuclear fusion experiment.

中性束注入加热是可控核聚变主要的辅助加热方式之一。

4·A numerical method simulating high current ion sources for neutral beam injection is given in this paper as well as its typical result.

本文叙述了中性束注入器中的强流离子源引出系统离子束光学性质的数值模拟方法，并给出了典型计算结果。

5·A key part of the neutral beam injector is ion beam system, whose property defines the efficiency and effect of the neutral beam injector.

中性束注入器的关键部分是离子束系统，它的性能决定了中性束注入的效率和效果。

6·A power supply system for diagnostic neutral beam on the HT-7 Tokamak was developed. Its logic control system based on S7-300 PLC was described.

文章介绍HT - 7托卡马克实验装置上的中性束诊断电源系统的组成、结构，以及基于S7 - 300 PLC的逻辑控制系统。

7·The system has been applied successfully in experiment and get many ideal results, which also provides a guarantee for the reliable running of diagnostic neutral beam.

系统成功地应用于实验并获得理想的实验结果，为诊断中性束稳态运行提供可靠保障。

8·The Neutral Beam Injection (NBI) system requires a clean high vacuum environment. The liquid helium cryocondensation pump with high pumping speed is an ideal vacuum obtain device.

中性束注入系统要求有洁净的动态高真空环境，大抽速液氦冷凝泵是满足此要求的理想真空获得设备。

9·This plane is therefore called the neutral surface of the beam.

因此这个平面称为梁的中性面。

10·The high plasma current allowed in a RFP is expected to be sufficient to heat the plasma to ignition without the need of auxiliary neutral-beam or radio-frequency heating.

在反场箍缩条件下可允许用强等离子体电流充分加热等离子体到点火温度，而不需要辅助的中性束或射频加热系统。