Results of ITER test blanket module mock-up experiments on DIII-D

Snipes, J. A.*; Schaffer, M. J.*; Gohil, P.*; de Vries, P.*; Fenstermacher, M. E.*; Evans, T. E.*; Gao, X. M.*; Garofalo, A.*; Gates, D. A.*; Greenfield, C. M.*; Heidbrink, W. W.*; Kramer, G. J.*; Liu, S.*; Loarte, A.*; Nave, M. F. F.*; Oyama, Naoyuki; Park, J.-K.*; Ramasubramanian, N.*; Reimerdes, H.*; Saibene, G.*; Salmi, A.*; Shinohara, Koji; Spong, D. A.*; Solomon, W. M.*; Tala, T.*; Boedo, J. A.*; Budny, R.*; Chuyanov, V.*; Doyle, E. J.*; Jakubowski, M.*; Jhang, H.*; Nazikian, R. M.*; Pustovitov, V. D.*; Schmitz, O.*; Osborne, T. H.*; Srinivasan, R.*; Taylor, T. S.*; Wade, M. R.*; You, K.-I.*; Zeng, L.*; DIII-D Team*

A series of experiments was performed on DIII-D to mock-up the field that will be induced in a pair of ferromagnetic Test Blanket Modules (TBMs) in ITER to determine the effects of such error fields on plasma operation and performance. A set of coils producing both poloidal and toroidal fields was placed inside a re-entrant horizontal port close to the plasma. The coils produce a localized ripple due to the toroidal field (TF) + TBM up to 5.7%, which is more than four times that expected from a pair of representative 1.3 ton TBMs in ITER. The experiments show that the reduction in the toroidal rotation is sensitive to the ripple. On the other hand, the confinement is reduced by up to 15-18% for local ripple 3% but is hardly affected at 1.7% local ripple.