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**Harvard**

Liu, Y., Akaslompolo, S., Cavinato, M., Koechl, F., Kurki-Suonio, T., Li, L., Parail, V., Saibene, G., Sarkimaki, K., Sipila, S. och Varje, J. (2016) *Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER*.

** BibTeX **

@article{

Liu2016,

author={Liu, Yueqiang and Akaslompolo, S. and Cavinato, M. and Koechl, F. and Kurki-Suonio, T. and Li, L. and Parail, V. and Saibene, G. and Sarkimaki, K. and Sipila, S. and Varje, J.},

title={Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER},

journal={Nuclear Fusion},

issn={0029-5515},

volume={56},

issue={6},

pages={Art. no. 066001},

abstract={Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations produced by ferritic inserts (FIs) and test blanket modules (TBMs) for four ITER plasma scenarios: the 15 MA baseline, the 12.5 MA hybrid, the 9 MA steady state, and the 7.5 MA half-field helium plasma. Due to the broad toroidal spectrum of the FI and TBM fields, the plasma response for all the n = 1-6 field components are computed and compared. The plasma response is found to be weak for the high-n (n > 4) components. The response is not globally sensitive to the toroidal plasma flow speed, as long as the latter is not reduced by an order of magnitude. This is essentially due to the strong screening effect occurring at a finite flow, as predicted for ITER plasmas. The ITER error field correction coils (EFCC) are used to compensate the n = 1 field errors produced by FIs and TBMs for the baseline scenario for the purpose of avoiding mode locking. It is found that the middle row of the EFCC, with a suitable toroidal phase for the coil current, can provide the best correction of these field errors, according to various optimisation criteria. On the other hand, even without correction, it is predicted that these n = 1 field errors will not cause substantial flow damping for the 15 MA baseline scenario.},

year={2016},

keywords={plasma response, 3D magnetic fields, ITER TBM},

}

** RefWorks **

RT Journal Article

SR Electronic

ID 238352

A1 Liu, Yueqiang

A1 Akaslompolo, S.

A1 Cavinato, M.

A1 Koechl, F.

A1 Kurki-Suonio, T.

A1 Li, L.

A1 Parail, V.

A1 Saibene, G.

A1 Sarkimaki, K.

A1 Sipila, S.

A1 Varje, J.

T1 Modelling of 3D fields due to ferritic inserts and test blanket modules in toroidal geometry at ITER

YR 2016

JF Nuclear Fusion

SN 0029-5515

VO 56

IS 6

AB Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations produced by ferritic inserts (FIs) and test blanket modules (TBMs) for four ITER plasma scenarios: the 15 MA baseline, the 12.5 MA hybrid, the 9 MA steady state, and the 7.5 MA half-field helium plasma. Due to the broad toroidal spectrum of the FI and TBM fields, the plasma response for all the n = 1-6 field components are computed and compared. The plasma response is found to be weak for the high-n (n > 4) components. The response is not globally sensitive to the toroidal plasma flow speed, as long as the latter is not reduced by an order of magnitude. This is essentially due to the strong screening effect occurring at a finite flow, as predicted for ITER plasmas. The ITER error field correction coils (EFCC) are used to compensate the n = 1 field errors produced by FIs and TBMs for the baseline scenario for the purpose of avoiding mode locking. It is found that the middle row of the EFCC, with a suitable toroidal phase for the coil current, can provide the best correction of these field errors, according to various optimisation criteria. On the other hand, even without correction, it is predicted that these n = 1 field errors will not cause substantial flow damping for the 15 MA baseline scenario.

LA eng

DO 10.1088/0029-5515/56/6/066001

LK http://dx.doi.org/10.1088/0029-5515/56/6/066001

OL 30