A path to stable low-torque plasma operation in ITER with test blanket modules

M. Lanctot, J.A. Snipes, H. Reimerdes, C. Paz-Soldan, N. Logan, J.M. Hanson, R,J. Buttery, J. deGrassie, A.M. Garofalo, T.K. Gray, B.A. Grierson, J.D. King, G.J. Kramer, R. La Haye, D.C. Pace, J.K. Park, Antti Salmi, S. Shiraki, E.J. Strait, W.M. SolomonTuomas Tala, M.A. Van Zeeland

    Research output: Contribution to journalArticleScientificpeer-review

    9 Citations (Scopus)


    New experiments in the low-torque ITER Q=10 scenario on DIII-D demonstrate that n=1 magnetic fields from a single row of ex-vessel control coils enable operation at ITER performance metrics in the presence of applied non-axisymmetric magnetic fields from a test blanket module (TBM) mock-up coil. With n=1 compensation, operation below the ITER-equivalent injected torque is successful at three times the ITER equivalent toroidal magnetic field ripple for a pair of TBMs in one equatorial port, whereas the uncompensated TBM field leads to rotation collapse, loss of H-mode and plasma current disruption. In companion experiments at high plasma beta, where the n=1 plasma response is enhanced, uncorrected TBM fields degrade energy confinement and the plasma angular momentum while increasing fast ion losses; however, disruptions are not routinely encountered owing to increased levels of injected neutral beam torque. In this regime, n=1 field compensation leads to recovery of a dominant fraction of the TBM-induced plasma pressure and rotation degradation, and an 80% reduction in the heat load to the first wall. These results show that the n=1 plasma response plays a dominant role in determining plasma stability, and that n=1 field compensation alone not only recovers most of the impact on plasma performance of the TBM, but also protects the first wall from potentially damaging heat flux. Despite these benefits, plasma rotation braking from the TBM fields cannot be fully recovered using standard error field control. Given the uncertainty in extrapolation of these results to the ITER configuration, it is prudent to design the TBMs with as low a ferromagnetic mass as possible without jeopardizing the TBM mission.
    Original languageEnglish
    Article number036004
    JournalNuclear Fusion
    Issue number3
    Publication statusPublished - 2017
    MoE publication typeA1 Journal article-refereed


    • test blanket modules
    • error fields
    • ITER
    • DIII-D


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