IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S.R. Mohanty , L. Saikia , N. Bharali , S. Kalita
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引用次数: 0

摘要

本研究旨在提高惯性静电约束聚变(IECF)装置的中子产生率。在此之前,我们已经实现了每秒 106 个中子的中子产生率,但为了更广泛地应用该装置,需要通过增加离子密度和能量来提高中子产生率。此外,还需要更稳定、约束时间更长的等离子体。我们将传统的单网格 IECF 设备与新型三网格设备进行了比较,以评估使用多网格进行离子约束的优势。我们使用 2D-3V XOOPIC 代码建立的计算模型表明,三网格装置的优化电势可显著提高离子约束能力。模型显示,与单栅设计中较为分散的离子分布相比,三栅设计能更有效地将离子束导向中心。静电场的变化会产生一个修正的电位井,从而形成高度集中的离子束,并通过特定的路径进行引导。初步实验结果表明,由于三栅系统的功能改进,中子产率(每秒 107 个中子)提高了一个数量级。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Role of additional grids on ion flow dynamics of an inertial electrostatic confinement fusion neutron source
The present study aims to enhance the performance of an inertial electrostatic confinement fusion (IECF) device in terms of neutron production rate. Previously, we achieved a neutron generation rate of 106 neutrons per second, but for broader applications of the device, higher neutron production is needed by increasing ion density and energy. Additionally, more stable and well-confined plasma with longer confinement times is essential. We compared a conventional single-grid IECF device to a new triple-grid version to assess the advantages of using multiple grids for ion confinement. Our computational models, using the 2D-3V XOOPIC code, indicate that the optimized potentials of the triple-grid device can significantly improve ion confinement. The models reveal that the triple-grid design more effectively channels ion beams toward the center, compared to the more dispersed ion distribution in the single-grid design. Alterations in the electrostatic fields generate a modified potential well, resulting in the formation of highly concentrated ion beams channeled through specific pathways. Preliminary experimental results indicate a one-order improvement in neutron yield (107 neutrons per second) due to the functional improvement in the triple-grid system.
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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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