Study of impurity behaviour for first magnetic configuration changes in W7-X plasmas by means of PHA spectra

Journal Article · 01 May 2018 · Fusion Engineering and Design

DOI: https://doi.org/10.1016/j.fusengdes.2018.04.119 · OSTI ID:1598040

Czarnecka, Agata ^[1]; Fornal, Tomasz ^[1]; Gruca, Marta ^[1]; Krawczyk, Natalia ^[1]; Kubkowska, Monika ^[1]; Jabłoński, Sławomir ^[1]; Ryć, Leszek ^[1]; Andreeva, Tamara ^[2]; Alonso, Arturo ^[2]; Burhenn, Rainer ^[2]; Buttenschön, Birger ^[2]; Dinklage, Andreas ^[2]; Jakubowski, Marcin ^[2]; Krychowiak, Maciej ^[2]; König, Ralph ^[2]; Pablant, Novimir ^[3]; Thomsen, Henning ^[2]; Zhang, Daihong ^[2]

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1. Inst. of Plasma Physics and Laser Microfusion, Warsaw (Poland)
2. Max Planck Inst. for Plasma Physics, Greifswald (Germany)
3. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Transport properties of impurities in stellarators are sensitive to potential variations on flux-surfaces, and thermodynamic forces from the bulk plasma which might be affected by changes in magnetic field properties. In this contribution, the effect of planar coil current changes on the core impurity behavior in the first operating phase of Wendelstein 7-X (W7-X) is described. Hydrogen plasmas, at different heating power levels were investigated showing Core-Electron-Root-Confinement (CERC) conditions, characterized by peaked Te profiles and positive radial electric fields in the plasma core. Additionally, impurity spectra in the x-ray emission range between 1 and 10 keV were measured by the Pulse Height Analysis (PHA) diagnostic. The line-integrated measurements of transitions in sulphur, chlorine and argon are in the focus of this analysis. First observations indicate that the scans of the magnetic configuration did not affect strongly the impurity concentration in the core. Clear differences in the impurity content, however, have been observed when the ECRH power was changed, which affects the bulk plasma properties.

• Research Organization: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
• Sponsoring Organization: USDOE; EUROfusion Consortium; Polish Ministry of Science and Higher Education
• Contributing Organization: W7-X Team
• Grant/Contract Number: AC02-09CH11466
• OSTI ID: 1598040
• Journal Information: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: PB Vol. 136; ISSN 0920-3796
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English