Advanced magnetic diagnostic coils based on TPC technology for COMPASS-U and EU-DEMO

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

Fusion Engineering and Design Pub Date : 2025-04-17 DOI:10.1016/j.fusengdes.2025.115070

Pavel Turjanica , Jan Reboun , Ivan Duran , Slavomir Entler , Ladislav Viererbl , Marek Simonovsky

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引用次数: 0

Abstract

Magnetic diagnostic coils based on Thick Printed Copper (TPC) technology for COMPASS-U and EU-DEMO fusion reactors are introduced in this paper. Special emphasis is placed on the aspects of design and technology qualification. Firstly, the results of the tests carried out to qualify the TPC technology for the Tokamak environment are presented. Dedicated test samples were designed and temperature cycling irradiation and adhesion tests including electrical parameters measurements were executed. The aim of the TPC coil design was to achieve a high effective sensor area (up to 0.25 m²) and small dimensions compared to conventional coils. The coils can be composed from materials as Cu and Al₂O₃, AlN, or spinel (Al₂MgO₄) which ensures compatibility with elevated temperatures (at least 500 °C) and intense neutron radiation. Two coil variants, 1st with low winding density and 2nd with high winding density are proposed. Advanced layout of high-density coil winding achieving high suppression factor of cross-field sensitivity is presented. In parallel, the winding layout is also optimized to reduce parasitic radiation and temperature gradient induced side effects. Preliminary results of irradiation tests and temperature cycling test of TPC low winding density coil are presented.

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基于TPC技术的先进磁诊断线圈用于COMPASS-U和EU-DEMO

介绍了一种基于厚印刷铜（TPC）技术的COMPASS-U和EU-DEMO聚变反应堆磁诊断线圈。特别强调的是设计和技术资格方面。首先，介绍了为使TPC技术适应托卡马克环境而进行的测试结果。设计了专用的测试样品，并进行了温度循环辐照和附着力测试，包括电气参数测量。与传统线圈相比，TPC线圈设计的目的是实现高效传感器面积（高达0.25 m2）和小尺寸。线圈可以由Cu和Al2O3， AlN或尖晶石（Al2MgO4）等材料组成，确保与高温（至少500°C）和强烈的中子辐射兼容。提出了低绕组密度和高绕组密度两种线圈变体。提出了高密度线圈绕组的先进布局，实现了高交叉场灵敏度的抑制系数。同时，还优化了绕组布局，以减少寄生辐射和温度梯度引起的副作用。介绍了TPC低缠绕密度线圈辐照试验和温度循环试验的初步结果。

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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.