体积中子源舱内屏蔽层的电磁设计优化

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ivan Alessio Maione , Christian Bachmann , Irene Pagani , Riccardo Lombroni
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引用次数: 0

摘要

这项工作提出了一套在体积中子源(VNS)上进行的电磁(EM)分析,这是一种设计用于在近反应堆条件下测试聚变反应堆组件的设施。该研究调查了瞬变电磁场景下屏蔽层、分流器、真空容器和热屏蔽等关键部件中的涡流、洛伦兹力和晕流分布。在ANSYS开发的有限元模型中实现了利用MAXFEA分析的垂直位移事件(VDEs)和环形场线圈快速放电(tfcfd)等关键事件,以计算诱发电磁载荷。重点是板内覆盖层的设计,通过优化电触点、改进材料配置和加入铁磁元件来满足附着系统的要求,从而减少电磁载荷。研究结果为VNS的结构改进和操作可行性提供了必要的反馈。该方法和发现通过解决电磁瞬变带来的关键挑战,为聚变反应堆设计做出了广泛贡献。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Electromagnetic design optimization of the inboard shielding blanket for the volumetric neutron source
This work presents a set of electromagnetic (EM) analyses performed on the Volumetric Neutron Source (VNS), a facility designed to test fusion reactor components under near-reactor conditions. The study investigates eddy currents, Lorentz forces, and halo current distributions in critical components such as the shield blanket, divertor, vacuum vessel, and thermal shield under transient electromagnetic scenarios. Key events such as Vertical Displacement Events (VDEs), analyzed using MAXFEA, and toroidal field coil fast discharges (TFCFDs) are implemented in finite element method models developed in ANSYS to calculate the induced EM loads.
Focus is given to the inboard blanket's design, with modifications to reduce EM loads by optimizing electrical contacts, refining material configurations, and incorporating ferromagnetic elements to satisfy the requirements for the attachment system. Results provide essential feedback for structural improvements and advancing the VNS toward operational feasibility. The methodology and findings contribute broadly to fusion reactor design by addressing critical challenges posed by EM transients.
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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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