Plasma and gas neutralisation of high energy H- and D- in an Argon plasma neutraliser

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-15 DOI:10.1016/j.fusengdes.2024.114578
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Abstract

A beam driven plasma neutraliser (BDPN) has been proposed [1] as a relatively simple way to increase the efficiency of neutral beam injectors based on the acceleration and neutralisation of H- or D-. Initial calculations showed that sufficient levels of ionisation could be achieved with H2 or D2 as the initial gas target in the neutraliser if a plasma confinement time of the plasma in the neutraliser is >0.5 ms could be achieved. However, later calculations [2,3] show that the afore-mentioned results were very optimistic as the calculations did not take into account the recombination of molecular ions with electrons. Hence, it has been suggested [4] to use an argon (Ar) plasma as the molecular ion content in such a plasma will be negligible. The use of an Ar plasma neutraliser has been suggested previously [[5], [6], [7]], but few details have been given of the obtainable neutralisation efficiency, the necessary line density for that neutralisation efficiency, or of the calculations and cross sections used to deduce those quantities. This paper briefly discusses why Ar could be a good choice for a plasma neutraliser, then the reactions occurring between the H-/D- beam and the particles in the Ar plasma, and the available cross section data for those reactions. Subsequently, the differential equations for the change of the species in the beam as it traverses an Ar plasma are deduced and solved, and the solutions used to calculate the achievable neutralisation efficiency as a function of the line density in the neutraliser etc. Results are given of the neutralisation efficiency as a function of the degree of ionisation in the neutraliser, the required line density, and the species changes in the beam for accelerated H- beams with 100, 500 and 870 keV energies.

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在氩等离子体中和器中对高能 H- 和 D- 进行等离子体和气体中和
有人提出了光束驱动等离子体中和器(BDPN)[1],认为这是一种相对简单的方法,可以在加速和中和 H- 或 D- 的基础上提高中性光束注入器的效率。最初的计算表明,如果中和器中等离子体的约束时间为 0.5 毫秒,那么以 H2 或 D2 作为中和器中的初始气体目标就可以实现足够水平的电离。然而,后来的计算[2,3]表明,上述结果非常乐观,因为计算没有考虑分子离子与电子的重组。因此,有人建议 [4] 使用氩(Ar)等离子体,因为这种等离子体中的分子离子含量可以忽略不计。以前曾有人建议使用氩等离子体中和器[[5]、[6]、[7]],但很少有人详细说明可获得的中和效率、中和效率所需的线密度或用于推导这些量的计算和截面。本文简要讨论了为什么氩可以作为等离子体中和器的良好选择,然后讨论了 H-/D- 射束与氩等离子体中的粒子之间发生的反应,以及这些反应的现有截面数据。随后,推导并求解了光束穿过氩等离子体时光束中物种变化的微分方程,并利用这些解法计算了作为中和器中线密度函数的可实现中和效率。结果显示了中和器中的电离程度、所需的线密度以及 100、500 和 870 千伏能量的加速 H- 光子束中的物种变化对中和效率的影响。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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