Optimization of the Laval nozzle for supersonic molecular beam injection by numerical simulation

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-08-30 DOI:10.1016/j.fusengdes.2025.115412

J.H. Qiao , B. Cao , Z.Y. He , W.K. Wang , J.S. Yuan , G.Z. Zuo

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Abstract

Supersonic molecular beam injection (SMBI) is an efficient and routine technique for plasma fueling in the Experimental Advanced Superconducting Tokamak (EAST). To further improve the efficiency of particle injection, the effect of the nozzle throat diameter, divergent section length, and divergent section angle on the beam characteristics is simulated. Furthermore, an experimental test platform with a moveable pitot tube is developed and implemented to validate the reliability and accuracy of the numerical simulation. The results demonstrate that nozzle dimensions are crucial in determining the characteristics of the beam as it enters the vacuum chamber. A divergent half angle of about 20° is found to produce the most concentrated number density distribution near the axis. Increasing the throat diameter and the divergent section length also extends the high-density region near the nozzle exit. This paper presents optimization strategies for the design of nozzles in SMBI systems, offering useful guidance for the design and application of SMBI in future fusion devices.

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超声速分子束喷射Laval喷嘴的数值模拟优化

超声速分子束注入（SMBI）是先进超导托卡马克（EAST）实验中一种高效、常规的等离子体加注技术。为了进一步提高颗粒喷射效率，模拟了喷嘴喉道直径、发散截面长度和发散截面角对光束特性的影响。为了验证数值模拟的可靠性和准确性，设计并实现了可动皮托管实验测试平台。结果表明，喷嘴的尺寸是决定光束进入真空室时的特性的关键。发现在轴附近，约20°的发散半角能产生最集中的数密度分布。增大喉部直径和发散截面长度也扩大了喷管出口附近的高密度区域。本文提出了SMBI系统喷嘴的优化设计策略，为SMBI在未来核聚变装置中的设计和应用提供了有益的指导。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.