The Preliminary Design of Large-Scale High-Intensity DC and Power Frequency Magnetic Field Immunity Test Platform
The electromagnetic interference caused by the strong stray magnetic field generated by a tokamak device and its coil power supply will greatly threaten the reliable operation of electrical and electronic devices nearby, and a magnetic field immunity test is the most commonly used method to qualify...
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Veröffentlicht in: | IEEE transactions on plasma science 2020-06, Vol.48 (6), p.1693-1697 |
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Sprache: | eng |
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Zusammenfassung: | The electromagnetic interference caused by the strong stray magnetic field generated by a tokamak device and its coil power supply will greatly threaten the reliable operation of electrical and electronic devices nearby, and a magnetic field immunity test is the most commonly used method to qualify the sensitive equipment and ensure the reliability of the system. Thus, building a high-intensity magnetic field immunity test platform is essential for the stable operation of a large tokamak device in the future. This article presents the preliminary design of a large-scale high-intensity magnetic field immunity test platform, including dc static test platform, dc transient test platform, and power frequency test platform. Referring to the actual magnetic field environment around the International Thermonuclear Experimental Reactor (ITER) tokamak device and its magnet power supply, the design parameters of the subplatforms are determined. Then the scheme design of the subplatforms and the integration design of the whole platform are briefly introduced. As a part of the large-scale superconductor rest facility (LSTF) in Chinese Academy of Science, Institute of Plasma Physics (ASIPP), the design takes full advantages of the other devices planned in the facility. This test platform will be the largest in the world and enable the test of various equipment under different magnetic field environments, and more importantly, play an important role in the reliable operation of China Fusion Engineering Test Reactor (CFETR) and future large tokamak devices. |
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ISSN: | 0093-3813 1939-9375 |
DOI: | 10.1109/TPS.2020.2982778 |