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首页> 外文期刊>Fusion Engineering and Design >Beam extraction characteristics of a low-energy, high-current pulsed ion source of a versatile experiment spherical torus neutral beam injector
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Beam extraction characteristics of a low-energy, high-current pulsed ion source of a versatile experiment spherical torus neutral beam injector

机译：多功能实验球形环形中性束注入器的低能量，高电流脉冲离子源的束提取特性

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摘要

A neutral beam (NB) ion source aimed to inject a 0.5-MW NB has been developed for Versatile Experiment Spherical Torus (VEST) plasma heating. Beam energy is generally limited to less than ∼20 keV to reduce particle orbit loss and beam shine-through. To meet this power demand, high-current ion beam extraction is important to achieve the required performance of the ion source. In this study, a 0.7-MW ion source was designed, fabricated, assembled, and optimized at the NB test stand in Korea Atomic Energy Research Institute (KAERI) considering the beam power losses in the beamline components. The ion source comprises a multicusped-bucket-type plasma generator and a multislot-triode-type ion accelerator with an extraction area of 12 cm × 46 cm. The characteristics of arc discharge and beam extraction were investigated using hydrogen gas to obtain the optimum operating parameters of the arc power, filament voltage, gas pressure, extraction voltage, and suppression voltage. The ion source was then conditioned and performance tests were primarily completed. Results of the experiments show that the ion source can extract sufficient ion beam power that is than 0.75 MW (50 A/15 keV) with 100-kW arc power. The arc efficiency and beam perveance were estimated to be 0.6 A/kW and 20–25 μP, respectively. Moreover, the design goal of delivering a 0.5-MW NB into the VEST plasma will be achievable based on the optimum operating conditions. This ion source has been installed in the VEST NB injection system at Seoul National University and its commissioning is ongoing.
机译：已开发出旨在注入0.5 MW NB的中性束（NB）离子源，用于多功能实验球形圆环（VEST）等离子体加热。通常将束能量限制在小于约20 keV，以减少粒子轨道损失和束穿透。为了满足此功率需求，高电流离子束提取对于实现离子源所需的性能很重要。在这项研究中，考虑到束线组件中的束功率损失，在韩国原子能研究院（KAERI）的NB测试台上设计，制造，组装并优化了0.7 MW离子源。离子源包括多尖端桶型等离子体发生器和多槽三极管型离子加速器，其提取面积为12 cm×46 cm。使用氢气研究了电弧放电和束提取的特性，以获得电弧功率，灯丝电压，气压，提取电压和抑制电压的最佳操作参数。然后对离子源进行调节，并初步完成了性能测试。实验结果表明，离子源在100 kW电弧功率下可以提取到比0.75 MW（50 A / 15 keV）更高的离子束功率。电弧效率和光束导通估计分别为0.6 A / kW和20-25P。此外，基于最佳工作条件，可以实现将0.5 MW NB输送到VEST等离子体中的设计目标。该离子源已安装在首尔国立大学的VEST NB注射系统中，正在调试中。

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