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Tuning of the rotational transform in Wendelstein 7-X

Lazerson, Samuel A.; Gao, Yu; Hammond, Kenneth; Killer, Carsten; Schlisio, Georg; Otte, Matthias; Biedermann, Christoph; Spolaore, Monica; Bozhenkov, Sergey; Geiger, Joachim; Grulke, Olaf; Nicolai, Dirk; Satheeswaran, Guruparan; Niemann, Holger; Jakubowski, Marcin; Drewelow, Peter; Sitjes, Aleix Puig; Ali, Adnan; Cannas, Barbara; Pisano, Fabio; Koenig, Ralph; Wurden, Glen; Kocsis, Gabor; Szepesi, Tamas; Wenzel, Uwe; Mulsow, Matthias; Rahbarnia, Kian; Schilling, Jonathan; Neuner, Ulrich; Andreeva, Tamara; Thomsen, Henning; Knauer, Jens; Brunner, Kai Jakob; Blackwell, Boyd; Endler, Michael; Klose, Soren; Rudischhauser, Lukas

The control of rotational transform in Wendelstein 7-X (W7-X) is key to both the island divertor operation and safety of plasma facing components. The island divenor concept in W7-X relies on an edge flux surface with rotational transform of t = 1 resonating with an intrinsic n/m = 5/5 resonance to form a five lobed island chain. This island chain intersects with divertor plates to give rise to the island divertor. Changes in the relative position of the rational surface and the divertor plates can result in changes in divenor performance, thus the control of the rotational transform is essential to operation of the W7-X device. During the first divertor campaign electromagnetic loads resulted in elastic deformations of the shaped modular stellarator coils. Such deformations made these coils more planar, reducing the vacuum rotational transform, subsequently shifting the t = 1 resonance outward. Unintended plasma wall interactions provided the first clear evidence of this effect during plasma operation. Flux surface measurements were utilized to estimate the correct level of current in the planar coils for correction of t, and found to be around similar to-100 A. Scans the planar coil current for iota correction were performed during plasma operation. These measurements suggest planar coil currents between -250 and similar to 0 A would place the strike lines at the designed distance from the pumping gaps. Divertor Langmuir and upstream probe measurements confirm these estimates along with measurements of divertor neutral gas pressure.

ID 407430
DOI 10.1088/1741-4326/ab3df0
PRODUCT TYPE Journal Article
LAST UPDATE 2022-09-21T16:56:22Z
EU PROJECT EUROfusion
TITLE Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
FOUNDING PROGRAM H2020
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