Non-disruptive error field measurement in DIII-D low safety factor plasmas and projection to ITER

Non-disruptive error field measurement in DIII-D low safety factor plasmas and projection to ITER

Previous experiments in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007) introduced a method to identify intrinsic error fields (EFs) in tokamaks with minimal disruption risk by promptly healing driven magnetic islands during the conventional ‘compass scan’. This paper presents recent experimen...

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Bibliographic Details
Main Authors: Q.M. Hu, N.C. Logan, C. Paz-Soldan, J. Barr, S.K. Kim, J. Hanson, Y.Z. Jiang, S.M. Yang, A. Bortolon, W. Choi, Y.Q. Liu, J.-K. Park, E.J. Strait, Q. Yu
Format: Article
Language:English
Published: IOP Publishing 2024-01-01
Series:Nuclear Fusion
Subjects:
error field measurement
disruption
ITER
Online Access:https://doi.org/10.1088/1741-4326/ad8def
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https://doi.org/10.1088/1741-4326/ad8def

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