基于射频离子源的紧凑型氘-氘中子发生器的新进展

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zhenqing Zhu , Yuzhong Qian , Mengmeng Li , Xin Tao , Zhi Dou , Bing Hong , Renli Zhu , Wei Xu , Lizhen Liang , Chundong Hu
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引用次数: 0

摘要

本文对基于射频离子源的小型氘-氘中子发生器进行了系统优化,使中子产率达到6.46 × 109 n/s,提高了6倍。设计的器件采用凹形高压真空馈通,将器件的总击穿强度提高到150kv。此外,为了提高提取的离子流,采用了一种创新的“扩散型”等离子体室,使光束提取增加了20%以上。此外,还验证了在高热负荷条件下,钪靶材的性能优于钛靶材,这主要是由于钪的氘解吸温度比钛高。最后,实现了大于5 × 109 n/s的稳定中子产率,有效运行时间超过98%。该结果为进一步提高中子成像质量提供了坚实的技术基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
New progress on a compact deuterium-deuterium neutron generator based on RF ion source
This article presents a systematic optimization of a compact deuterium-deuterium neutron generator based on a RF ion source, significantly increasing the neutron yield by 6 times to 6.46 × 109 n/s. The designed device employs a concave high-voltage vacuum feedthrough, increasing the overall breakdown strength of the device to 150 kV. Additionally, to improve the ion current extracted, an innovative ‘diffusion-type’ plasma chamber has been adopted, achieving an increase of over 20 % in beam extraction. Furthermore, it has been verified that under high thermal load conditions, the performance of the scandium target is superior to that of the titanium target, primarily due to the higher desorption temperature of deuterium from scandium compared to titanium. Finally, a stable neutron yield of over 5 × 109 n/s was achieved, with an effective operating time exceeding 98 %. This result provides a solid technical foundation for further improving neutron imaging quality.
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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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