用于 INTF ITER DNB 原型的瓷基 100kV 贯穿件

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-30 DOI:10.1016/j.fusengdes.2024.114609
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引用次数: 0

摘要

国际热核聚变实验堆印度测试设施(INTF)的诊断中性束(DNB)高压套管(HVB)是一种瓷基 100 kV 真空馈入件。它将用于将来自高压甲板的高压(HV)电源馈入光束源(BS),以便在高真空条件下产生 100 kV H 光束:1.将 100 kV 馈线与接地容器隔离;2.2. 与 25 个不同类型的馈线贯穿件形成真空边界。INTF HVB 的设计针对真空、机械和电气要求进行了严格的迭代优化设计。设计完成后,INTF HVB 的开发需要进行多次原型设计活动,以解决以下挑战:建立具有高真空兼容性的适当粘接方法、大型(直径 800 毫米,高度 530 毫米)绝缘体的处理程序、对绝缘体椭圆形的竣工公差进行事先评估,以及在各个步骤进行测试和鉴定,以制定制造和组装的实施计划。因此,在制造过程中采用了以原型设计为基础的技术来解决难题,从而成功开发出了 HVB。
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Porcelain based 100kV feedthrough for prototype ITER DNB at INTF

High Voltage Bushing (HVB) of the Indian Test Facility (INTF) of ITER Diagnostic Neutral Beam (DNB) is a porcelain-based 100 kV vacuum feedthrough. This will be used to feed the High Voltage (HV) supplies, coming from the HV deck to the Beam Source (BS) for the production of 100 kV H- beam under high vacuum, therefore, it has two major functions: 1. Isolate 100 kV feedlines from grounded vessel and 2. Forms vacuum boundary with 25 feedline penetrations of different kinds. INTF HVB has been designed with rigorous iterations of design optimization for vacuum, mechanical, and electrical requirements. After design, the development of INTF HVB required several prototyping activities to address the challenges in establishing the appropriate bonding methodology with high vacuum compatibility, handling procedure of large size (∼800 mm diameter and 530 mm height) insulator, prior assessments of tolerances due to as-built ovality in insulator and testing & qualification at various steps, to establish the implementation plan for manufacturing and assembly. As a result, techniques, based on prototyping, manifest to solve the challenges were utilized in the manufacturing, leading to the successful development of the HVB.

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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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