工艺NNBI用SF6气体绝缘高压套管的设计与分析

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

Fusion Engineering and Design Pub Date : 2025-10-08 DOI:10.1016/j.fusengdes.2025.115468

Yuchen Qu , Zhimin Liu , Caichao Jiang , Jianglong Wei , Bo Liu , Yuanlai Xie , Xu Wang

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引用次数: 0

摘要

CRAFT NNBI的全尺寸束流源计划采用真空绝缘离子源方案，通过-200 kv的两级加速电压产生400 keV的负氢离子束。初步设计已经开发了两级-400千伏高压套管，用于sf6绝缘传输线和真空室之间的绝缘和密封连接。进行真空侧绝缘设计，对真空侧阴极面、阳极面、绝缘子面、三相点的电场强度进行分析和改进，满足日本原子能机构对ITER高压套管设计的标准要求。本设计包括- 200kvv套管段的冷却水流道，考虑了加速电极热负荷和温度约束对冷却水流量的要求，分析了通道内的压降和流量分布的均匀性。考虑输电线中0.6 MPa的SF6气体、绝缘陶瓷环与FRP环之间1 MPa的空气以及重力载荷作用下的应力和变形，对套管结构进行了机械强度分析。

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Design and analysis of a SF6 gas insulating HV-bushing for CRAFT NNBI

The full-scale beam source of CRAFT NNBI is planned to adopt a vacuum-insulated ion source scheme to generate a 400 keV negative hydrogen ion beam through two stages of -200 kVacceleration voltage. A preliminary design has been developed for two stages of -400 kVhigh-voltage bushings, which are intended for insulating and sealing connections between the SF6-insulated transmission line and the vacuum chamber. Vacuum-side insulation design has been conducted to analyze and improve the electric field strength of the vacuum-side cathode surface, anode surface, insulator surface, and triple point, meeting the standard requirements specified by the Japan Atomic Energy Agency for high-voltage bushings designed for ITER. The design includes the cooling water flow channels for the -200 kVbushing section, considering the requirements for cooling water flow rate based on the thermal load of the accelerating electrode (AG) and temperature constraints, analyzing pressure drop in the channels and uniformity of flow distribution. Mechanical strength analysis of the bushing structure has been performed, considering the stress and deformation under 0.6 MPa SF6 gas in the transmission line, 1 MPa air between the insulating ceramic ring and fiber-reinforced polymer (FRP) ring and gravity loads.

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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.