紧凑型D-D中子发生器高性能钛靶的结构设计与热分析

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chenglong Geng , Wei Xu , Zinan Feng , Weihai Wang , Xu Li , Chenlun Liao , Mengmeng Li , Xiancai Meng , Lizhen Liang , Chundong Hu
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引用次数: 0

摘要

钛靶是加速器驱动中子发生器的关键部件。在射束过程中,热沉积在靶材表面,导致靶材表面温度升高。植入靶材钛膜中的氘在温度超过200℃时显著释放。本文提出了三种不同的冷却概念,并对D-D中子发生器的热负荷和变形进行了模拟。通过优化靶内冷却剂通道的结构,提高了靶内热负荷的去除能力。当氘束注入功率为600 W时,通过双螺旋冷却结构将靶表面温度控制在73.7℃。当冷却剂流速达到19 m/s时,传递给冷却剂的热功率增大。此外,目标冷却剂通道的深度不影响热负荷的去除能力。最后,应用双螺旋冷却剂结构钛靶进行了稳定运行7 h的5 × 108 n/s中子产率实验。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Structural design and thermal analysis of high-performance titanium targets for compact D-D neutron generator
The titanium target is key component in accelerator-driven neutron generators. During beam injection, heat is deposited on the target surface, resulting in increasing of the surface temperature of the target. Deuterium implanted in the titanium film of the target is released significantly when the temperature exceeds 200°C. This work presents three different cooling concepts and simulations of heat load and deformation for D-D neutron generator. The heat load removal capability is improved by optimizing the structure of the coolant channel inside the target. The maximum target surface temperature was controlled at 73.7°C when the deuterium beam injection power was 600 W via a double-spiral cooling structure. It was found the thermal power transferred to the coolant increases with the coolant flow up to coolant velocity equal to 19 m/s. Moreover, the depth of the target coolant channel does not affect the heat load removal capability. Finally, a 5 × 108 n/s neutron yield experiment with steady operation for 7 h was performed with the application of the double-spiral coolant structure titanium target.
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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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