MITICA首次高压真空绝缘试验的进展和结果

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-07-23 DOI:10.1016/j.fusengdes.2025.115349

T. Patton , G. Chitarin , N. Pilan , M. Agostini , D. Aprile , M. Boldrin , V. Candeloro , M. Dan , S. Denizeau , N. Marconato , A. Rigoni , G. Manduchi , F. Santoro , E. Spada , C. Taliercio , L. Trevisan , M. Valente , L. Zanotto , P. Barbato , M. Fincato , M. Kashiwagi

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引用次数: 0

摘要

ITER的加热中性束注入器（HNB）包括一个束源（BS），被一个真空间隙包围，工作电压高达1mv。MITICA(兆伏特ITER注入器；概念推进（Concept Advancement）是ITER加热中性束（HNBs）的全尺寸原型，致力于测试和优化设计，目前正在帕多瓦的中性束测试设施（NBTF）中建造，该设施由Consorzio RFX主办。最近在日本茨城市Naka的QST实验室对MITICA和缩小尺寸模型的高压套管进行的实验表明，HNB绝缘的击穿概率可能至关重要。作为HNB作业的风险缓解措施，在NBTF的MITICA试验台进行了具体的高压测试。使用了全尺寸的“模拟电极”，再现了MITICA/HNB加速器的外部几何形状，允许在现实条件下快速实施和测试不同的静电配置。主要目标是：(1)验证当前设计中真空电极绝缘的性能；(2)评估必要的最小修改集，可能包括引入中间静电屏蔽。在MITICA真空容器中安装实际光束源之前的时间窗口内，预计所有测试都将进行。本文介绍了测试策略和诊断的特别开发，包括真空电流传感器，集成视频摄像机系统和数据采集网络，致力于识别大型真空容器内可能发生绝缘击穿的最关键区域。然后，就绝缘的最大耐压、电极几何形状、施加电压上升时间和真空调节程序的关系，提出并讨论了第一次测试活动的结果。

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Progress and results of the first high voltage vacuum insulation tests in MITICA

The Heating Neutral Beam injector (HNB) for ITER includes a Beam Source (BS) surrounded by a single vacuum gap, operating up to 1 MV total voltage. MITICA (Megavolt ITER Injector & Concept Advancement) is a full-scale prototype of the ITER Heating Neutral Beams (HNBs), devoted to test and optimize the design, under construction in Padova at the Neutral Beam Test Facility (NBTF) hosted by the Consorzio RFX.

Recent experiments on HV bushing for MITICA and reduced-scale models at QST lab in Naka, Ibaraki, Japan, indicate that the breakdown probability of the HNB insulation might be critical.

As a risk-mitigation measure for the HNB operation, a specific high-voltage test campaign has been undertaken in the MITICA test bed at NBTF. Full-size "mock-up electrodes", reproducing the outer geometry of the MITICA/HNB accelerator are used, allowing swift implementation and test of different electrostatic configurations in realistic conditions.

The main objectives are: (1) to verify the performance of the vacuum electrode insulation in the present design and: (2) to assess the minimal set of necessary modifications, possibly including the introduction of an intermediate electrostatic shield. All tests are foreseen during the time window before the installation of the real beam source in the MITICA vacuum vessel.

The paper describes the test strategy and the ad-hoc development of diagnostics, including current sensors in vacuum, integrated video camera system and data acquisition network, devoted to identify the most critical regions where an insulation breakdown could occur inside the large vacuum vessel.

Then, the results of the first test campaigns are presented and discussed, in terms of maximum withstand voltage of the insulation, in relation to electrode geometry, applied voltage rise time and vacuum conditioning procedure.

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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.