Initial development of the DIII–D snowflake divertor control. (11th April 2018)

• Record Type: Journal Article
• Authors: Kolemen, E.; Vail, P.J.; Makowski, M.A.; Allen, S.L.; Bray, B.D.; Fenstermacher, M.E.; Humphreys, D.A.; Hyatt, A.W.; Lasnier, C.J.; Leonard, A.W.; McLean, A.G.; Maingi, R.; Nazikian, R.; Petrie, T.W.; Soukhanovskii, V.A.; Unterberg, E.A.
• Is Part Of: Nuclear fusion. Volume 58:Number 6(2018:Jun.)
• Publication Date: 2018-04-11
• Subjects: advanced divertor -- divertor -- control -- snowflake -- DIII-D; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/aab0d3
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: Simultaneous control of two proximate magnetic field nulls in the divertor region is demonstrated on DIII–D to enable plasma operations in an advanced magnetic configuration known as the snowflake divertor (SFD). The SFD is characterized by a second-order poloidal field null, created by merging two first-order nulls of the standard divertor configuration. The snowflake configuration has many magnetic properties, such as high poloidal flux expansion, large plasma-wetted area, and additional strike points, that are advantageous for divertor heat flux management in future fusion reactors. However, the magnetic configuration of the SFD is highly-sensitive to changes in currents within the plasma and external coils and therefore requires complex magnetic control. The first real-time snowflake detection and control system on DIII–D has been implemented in order to stabilize the configuration. The control algorithm calculates the position of the two nulls in real-time by locally-expanding the Grad–Shafranov equation in the divertor region. A linear relation between variations in the poloidal field coil currents and changes in the null locations is then analytically derived. This formulation allows for simultaneous control of multiple coils to achieve a desired SFD configuration. It is shown that the control enabled various snowflake configurations on DIII–D in scenarios such as the double-null advanced tokamak. The SFD resulted in a 2.5× reduction in the peak heat flux for many energy confinement times (2–3 s) without any adverse effects on core plasma performance.