U.S. Department of EnergyOffice of Scientific and Technical Information
Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U
Abstract
The upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a larger center-stack, enabling higher toroidal field and longer pulse duration, and the addition of three new tangentially aimed neutral beam sources, which increase available heating and current drive, and allow for flexibility in shaping power, torque, current, and particle deposition profiles. To best use these new capabilities and meet the high-performance operational goals of NSTX-U, major upgrades to the NSTX-U Control System (NCS) hardware and software have been made. Several control algorithms, including those used for real-time equilibrium reconstruction and shape control, have been upgraded to improve and extend plasma control capabilities. As part of the commissioning phase of first plasma operations, the shape control system was tuned to control the boundary in both inner-wall limited and diverted discharges. It has been used to accurately track the requested evolution of the boundary (including the size of the inner gap between the plasma and central solenoid, which is a challenge for the ST configuration), X-point locations, and strike point locations, enabling repeatable discharge evolutions for scenario development and diagnostic commissioning.
- Authors:
- Publication Date:
- DOE Contract Number:
- AC02-09CH11466
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- U. S. Department of Energy
- OSTI Identifier:
- 1562092
- DOI:
- https://doi.org/10.11578/1562092
Citation Formats
Boyer, M, Battaglia, D, Mueller, D, Eidietis, N, Erickson, K, Ferron, J, Gates, D, Gerhardt, S, Johnson, R, Kolemen, E, Menard, J, Myers, C, Sabbagh, S, Scotti, F, and Vail, P. Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U. United States: N. p., 2018.
Web. doi:10.11578/1562092.
Boyer, M, Battaglia, D, Mueller, D, Eidietis, N, Erickson, K, Ferron, J, Gates, D, Gerhardt, S, Johnson, R, Kolemen, E, Menard, J, Myers, C, Sabbagh, S, Scotti, F, & Vail, P. Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U. United States. doi:https://doi.org/10.11578/1562092
Boyer, M, Battaglia, D, Mueller, D, Eidietis, N, Erickson, K, Ferron, J, Gates, D, Gerhardt, S, Johnson, R, Kolemen, E, Menard, J, Myers, C, Sabbagh, S, Scotti, F, and Vail, P. 2018.
"Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U". United States. doi:https://doi.org/10.11578/1562092. https://www.osti.gov/servlets/purl/1562092. Pub date:Thu Mar 01 00:00:00 EST 2018
@article{osti_1562092,
title = {Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U},
author = {Boyer, M and Battaglia, D and Mueller, D and Eidietis, N and Erickson, K and Ferron, J and Gates, D and Gerhardt, S and Johnson, R and Kolemen, E and Menard, J and Myers, C and Sabbagh, S and Scotti, F and Vail, P},
abstractNote = {The upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a larger center-stack, enabling higher toroidal field and longer pulse duration, and the addition of three new tangentially aimed neutral beam sources, which increase available heating and current drive, and allow for flexibility in shaping power, torque, current, and particle deposition profiles. To best use these new capabilities and meet the high-performance operational goals of NSTX-U, major upgrades to the NSTX-U Control System (NCS) hardware and software have been made. Several control algorithms, including those used for real-time equilibrium reconstruction and shape control, have been upgraded to improve and extend plasma control capabilities. As part of the commissioning phase of first plasma operations, the shape control system was tuned to control the boundary in both inner-wall limited and diverted discharges. It has been used to accurately track the requested evolution of the boundary (including the size of the inner gap between the plasma and central solenoid, which is a challenge for the ST configuration), X-point locations, and strike point locations, enabling repeatable discharge evolutions for scenario development and diagnostic commissioning.},
doi = {10.11578/1562092},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {3}
}
Works referenced in this record:
ELM elimination with Li powder injection in EAST discharges using the tungsten upper divertor
journal, January 2018
- Maingi, R.; Hu, J. S.; Sun, Z.
- Nuclear Fusion, Vol. 58, Issue 2
Works referencing / citing this record:
ELM elimination with Li powder injection in EAST discharges using the tungsten upper divertor
journal, January 2018
- Maingi, R.; Hu, J. S.; Sun, Z.
- Nuclear Fusion, Vol. 58, Issue 2