Optimization of a large-area grid electrode for negative ion source in fusion neutral beam injector

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jinhong Wang, Yan Wang, Yuwen Yang, Yuming Gu, Yahong Xie, Lizhen Liang, Jianglong Wei
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引用次数: 0

Abstract

At present, the CRAFT (Comprehensive Research Facility for Fusion Technology) dual-driver negative ion source for neutral beam injection applications has made progress. In order to solve the problem of heat removal function in large-area extraction grid, the multi-physics simulation, manufacturing and testing are carried out. Two simulation conditions before Cs seeding (J∼350 A/m, J-∼50 A/m) and after sufficient Cs conditioning (J∼150 A/m, J-∼250 A/m) were considered to evaluate the power load on EG, which peak power density were 11 and 6 MW/m respectively and were concentrated on locate near the two aperture rows. This paper mainly studies three designs of minor cooling channels (double bending channels, double straight channels, and single straight channel). First, the grid temperature, thermal stress and thermal deformation are compared with an inlet water rate of 1.21 kg/s at 35 °C, and the channel forming methods and welding types mechanisms are compared. The simulation results show that the thermos-mechanical property of double bending channels is the best, and that of double straight channels is slightly worse. In terms of processing and manufacturing, the yield of double bending channels is lower than double straight channels, and it is easy to leak during the experiment.
聚变中性束注入器负离子源大面积网格电极的优化
目前,用于中性束注入应用的 CRAFT(聚变技术综合研究设施)双驱动负离子源已取得进展。为了解决大面积萃取栅的散热功能问题,进行了多物理场仿真、制造和测试。考虑了铯播种前(J∼350 A/m,J-∼50 A/m)和铯充分调节后(J∼150 A/m,J-∼250 A/m)两种模拟条件,以评估 EG 的功率负荷,其峰值功率密度分别为 11 MW/m和 6 MW/m,并集中在两排孔附近。本文主要研究了三种小冷却通道设计(双弯曲通道、双直线通道和单直线通道)。首先,比较了 35 °C、进水速度为 1.21 kg/s 时的栅格温度、热应力和热变形,并比较了通道形成方法和焊接类型机制。模拟结果表明,双弯曲水道的热机械性能最好,双直水道的热机械性能稍差。在加工制造方面,双弯曲槽钢的成品率低于双直槽钢,且在实验过程中容易发生泄漏。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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