Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U

Boyer, M. D.; Battaglia, D. J.; Mueller, D.; Eidietis, N.; Erickson, K.; Ferron, J.; Gates, D. A.; Gerhardt, S.; Johnson, R.; Kolemen, E.; Menard, J.; Myers, C. E.; Sabbagh, S. A.; Scotti, F.; Vail, P.

doi:10.1088/1741-4326/aaa4d0

Title: Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U

Journal Article · Thu Jan 25 00:00:00 EST 2018 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/aaa4d0· OSTI ID:1419785

^[1];

^[1]; Mueller, D. ^[1];

^[2]; Erickson, K. ^[1]; Ferron, J. ^[2]; Gates, D. A. ^[1]; Gerhardt, S. ^[1]; Johnson, R. ^[2]; Kolemen, E. ^[3];

^[1];

^[1]; Sabbagh, S. A. ^[4]; Scotti, F. ^[5]; Vail, P. ^[3]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
General Atomics, San Diego, CA (United States)
Princeton Univ., Princeton, NJ (United States)
Columbia Univ., New York, NY (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Here, 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.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC02-09CH11466; AC52-07NA27344

OSTI ID:: 1419785

Alternate ID(s):: OSTI ID: 1860804

Report Number(s):: PPPL-5441; LLNL-JRNL-748328; TRN: US1801392

Journal Information:: Nuclear Fusion, Vol. 58, Issue 3; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 15 works

Citation information provided by
Web of Science

References (43)

Energy confinement scaling in the low aspect ratio National Spherical Torus Experiment (NSTX) Kaye, S. M.; Bell, M. G.; Bell, R. E. Nuclear Fusion, Vol. 46, Issue 10 https://doi.org/10.1088/0029-5515/46/10/002	journal	August 2006
Status of the control system on the National Spherical Torus Experiment (NSTX) Gates, D. A.; Ferron, J. R.; Bell, M. Fusion Engineering and Design, Vol. 81, Issue 15-17 https://doi.org/10.1016/j.fusengdes.2006.04.060	journal	July 2006
Real time equilibrium reconstruction for tokamak discharge control Ferron, J. R.; Walker, M. L.; Lao, L. L. Nuclear Fusion, Vol. 38, Issue 7 https://doi.org/10.1088/0029-5515/38/7/308	journal	July 1998
Full toroidal imaging of non-axisymmetric plasma material interaction in the National Spherical Torus Experiment divertor Scotti, Filippo; Roquemore, A. L.; Soukhanovskii, V. A. Review of Scientific Instruments, Vol. 83, Issue 10 https://doi.org/10.1063/1.4739510	journal	October 2012
First results from MAST Sykes, A.; Akers, R. J.; Appel, L. C. Nuclear Fusion, Vol. 41, Issue 10 https://doi.org/10.1088/0029-5515/41/10/310	journal	October 2001
Vessel eddy current measurement for the National Spherical Torus Experiment Gates, D. A.; Menard, J. E.; Marsala, R. J. Review of Scientific Instruments, Vol. 75, Issue 12 https://doi.org/10.1063/1.1813091	journal	December 2004
Magnetic diagnostics for equilibrium reconstruction and realtime plasma control in NSTX-Upgrade Gerhardt, S. P.; Erickson, K.; Kaita, R. Review of Scientific Instruments, Vol. 85, Issue 11 https://doi.org/10.1063/1.4889781	journal	November 2014
Experimental studies on fast-ion transport by Alfvén wave avalanches on the National Spherical Torus Experiment Podestà, M.; Heidbrink, W. W.; Liu, D. Physics of Plasmas, Vol. 16, Issue 5 https://doi.org/10.1063/1.3080724	journal	May 2009
Improved H-mode access in connected DND in MAST Meyer, H.; Carolan, P. G.; Conway, N. J. Plasma Physics and Controlled Fusion, Vol. 47, Issue 6 https://doi.org/10.1088/0741-3335/47/6/008	journal	May 2005
Simultaneous feedback control of plasma rotation and stored energy on NSTX-U using neoclassical toroidal viscosity and neutral beam injection Goumiri, I. R.; Rowley, C. W.; Sabbagh, S. A. Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4976853	journal	May 2017
Modeling fast-ion transport during toroidal Alfvén eigenmode avalanches in National Spherical Torus Experiment Fredrickson, E. D.; Crocker, N. A.; Bell, R. E. Physics of Plasmas, Vol. 16, Issue 12 https://doi.org/10.1063/1.3265965	journal	December 2009
Stability at high performance in the MAST spherical tokamak Buttery, R. J.; Akers, R.; Arends, E. Nuclear Fusion, Vol. 44, Issue 9 https://doi.org/10.1088/0029-5515/44/9/012	journal	August 2004
Plasma shape and position control in highly elongated tokamaks Hofmann, F.; Jardin, S. C. Nuclear Fusion, Vol. 30, Issue 10 https://doi.org/10.1088/0029-5515/30/10/003	journal	October 1990
Macroscopic stability of high β MAST plasmas Chapman, I. T.; Cooper, W. A.; Graves, J. P. Nuclear Fusion, Vol. 51, Issue 7 https://doi.org/10.1088/0029-5515/51/7/073040	journal	June 2011
Collisionality and safety factor scalings of H-mode energy transport in the MAST spherical tokamak Valovič, M.; Akers, R.; de Bock, M. Nuclear Fusion, Vol. 51, Issue 7 https://doi.org/10.1088/0029-5515/51/7/073045	journal	June 2011
Strike point control for the National Spherical Torus Experiment (NSTX) Kolemen, E.; Gates, D. A.; Rowley, C. W. Nuclear Fusion, Vol. 50, Issue 10 https://doi.org/10.1088/0029-5515/50/10/105010	journal	September 2010
Feedback control design for non-inductively sustained scenarios in NSTX-U using TRANSP Boyer, M. D.; Andre, R. G.; Gates, D. A. Nuclear Fusion, Vol. 57, Issue 6 https://doi.org/10.1088/1741-4326/aa68e9	journal	April 2017
Resistive wall stabilized operation in rotating high beta NSTX plasmas Sabbagh, S. A.; Sontag, A. C.; Bialek, J. M. Nuclear Fusion, Vol. 46, Issue 5 https://doi.org/10.1088/0029-5515/46/5/014	journal	April 2006
Implementation of β _N Control in the National Spherical Torus Experiment Gerhardt, S. P.; Mastrovito, D.; Bell, M. G. Fusion Science and Technology, Vol. 61, Issue 1 https://doi.org/10.13182/FST12-A13336	journal	January 2012
Overview of recent physics results from the National Spherical Torus Experiment (NSTX) Menard, J. E.; Bell, M. G.; Bell, R. E. Nuclear Fusion, Vol. 47, Issue 10 https://doi.org/10.1088/0029-5515/47/10/S13	journal	September 2007
Fusion nuclear science facilities and pilot plants based on the spherical tokamak Menard, J. E.; Brown, T.; El-Guebaly, L. Nuclear Fusion, Vol. 56, Issue 10 https://doi.org/10.1088/0029-5515/56/10/106023	journal	August 2016
A flexible software architecture for tokamak discharge control systems Ferron, J. R.; Penaflor, B.; Walker, M. L. Proceedings of 16th International Symposium on Fusion Engineering https://doi.org/10.1109/FUSION.1995.534361	conference	January 1995
Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator Menard, J. E.; Bromberg, L.; Brown, T. Nuclear Fusion, Vol. 51, Issue 10 https://doi.org/10.1088/0029-5515/51/10/103014	journal	August 2011
Modeling and control of plasma rotation for NSTX using neoclassical toroidal viscosity and neutral beam injection Goumiri, I. R.; Rowley, C. W.; Sabbagh, S. A. Nuclear Fusion, Vol. 56, Issue 3 https://doi.org/10.1088/0029-5515/56/3/036023	journal	February 2016
Equilibrium properties of spherical torus plasmas in NSTX Sabbagh, S. A.; Kaye, S. M.; Menard, J. Nuclear Fusion, Vol. 41, Issue 11 https://doi.org/10.1088/0029-5515/41/11/309	journal	November 2001
Recent experiments on Alfvén eigenmodes in MAST Gryaznevich, M. P.; Sharapov, S. E.; Lilley, M. Nuclear Fusion, Vol. 48, Issue 8 https://doi.org/10.1088/0029-5515/48/8/084003	journal	June 2008
Overview of results from the National Spherical Torus Experiment (NSTX) Gates, D. A.; Ahn, J.; Allain, J. Nuclear Fusion, Vol. 49, Issue 10 https://doi.org/10.1088/0029-5515/49/10/104016	journal	September 2009
A reduced resistive wall mode kinetic stability model for disruption forecasting Berkery, J. W.; Sabbagh, S. A.; Bell, R. E. Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4977464	journal	May 2017
Plasma modelling results and shape control improvements for NSTX Kolemen, E.; Gates, D. A.; Gerhardt, S. Nuclear Fusion, Vol. 51, Issue 11 https://doi.org/10.1088/0029-5515/51/11/113024	journal	November 2011
Overview of the physics and engineering design of NSTX upgrade Menard, J. E.; Gerhardt, S.; Bell, M. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083015	journal	July 2012
Collective fast ion instability-induced losses in National Spherical Tokamak Experiment Fredrickson, E. D.; Bell, R. E.; Darrow, D. S. Physics of Plasmas, Vol. 13, Issue 5 https://doi.org/10.1063/1.2178788	journal	May 2006
NSTX-U Control System Upgrades Erickson, K. G.; Gates, D. A.; Gerhardt, S. P. Fusion Engineering and Design, Vol. 89, Issue 6 https://doi.org/10.1016/j.fusengdes.2014.04.069	journal	June 2014
Digital Coil Protection System (DCPS) algorithms for the NSTX centerstack upgrade Woolley, R. D.; Titus, P. H.; Neumeyer, C. L. 2011 IEEE 24th Symposium on Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on Fusion Engineering https://doi.org/10.1109/SOFE.2011.6052262	conference	June 2011
Scaling of Electron and Ion Transport in the High-Power Spherical Torus NSTX Kaye, S. M.; Bell, R. E.; Gates, D. Physical Review Letters, Vol. 98, Issue 17 https://doi.org/10.1103/PhysRevLett.98.175002	journal	April 2007
Confinement and local transport in the National Spherical Torus Experiment (NSTX) Kaye, S. M.; Levinton, F. M.; Stutman, D. Nuclear Fusion, Vol. 47, Issue 7 https://doi.org/10.1088/0029-5515/47/7/001	journal	June 2007
Dependence of the L–H transition on X-point geometry and divertor recycling on NSTX Battaglia, D. J.; Chang, C. S.; Kaye, S. M. Nuclear Fusion, Vol. 53, Issue 11 https://doi.org/10.1088/0029-5515/53/11/113032	journal	October 2013
An overview of recent physics results from NSTX Kaye, S. M.; Abrams, T.; Ahn, J. -W. Nuclear Fusion, Vol. 55, Issue 10 https://doi.org/10.1088/0029-5515/55/10/104002	journal	March 2015
Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction Gates, D. A.; Ferron, J. R.; Bell, M. Nuclear Fusion, Vol. 46, Issue 1 https://doi.org/10.1088/0029-5515/46/1/002	journal	December 2005
Overview of L–H power threshold studies in NSTX Maingi, R.; Kaye, S. M.; Bell, R. E. Nuclear Fusion, Vol. 50, Issue 6 https://doi.org/10.1088/0029-5515/50/6/064010	journal	May 2010
Exploration of spherical torus physics in the NSTX device Ono, M.; Kaye, S. M.; Peng, Y. -K. M. Nuclear Fusion, Vol. 40, Issue 3Y https://doi.org/10.1088/0029-5515/40/3Y/316	journal	March 2000
Overview of NSTX Upgrade initial results and modelling highlights Menard, J. E.; Allain, J. P.; Battaglia, D. J. Nuclear Fusion, Vol. 57, Issue 10, Article No. 102006 https://doi.org/10.1088/1741-4326/aa600a	journal	June 2017
Progress towards steady state at low aspect ratio on the National Spherical Torus Experiment (NSTX) Gates, D. A.; Menard, J.; Maingi, R. Nuclear Fusion, Vol. 47, Issue 9 https://doi.org/10.1088/0029-5515/47/9/040	journal	September 2007
Multivariable Multi-model-based magnetic control system for the current ramp-up phase in the National Spherical Torus Experiment (NSTX) Shi, Wenyu; Barton, Justin; Alsarheed, Majed 2011 50th IEEE Conference on Decision and Control and European Control Conference (CDC-ECC 2011) https://doi.org/10.1109/CDC.2011.6161259	conference	December 2011

Cited By (6)

A scalable real-time framework for Thomson scattering analysis: Application to NSTX-U Laggner, F. M.; Diallo, A.; LeBlanc, B. P. Review of Scientific Instruments, Vol. 90, Issue 4 https://doi.org/10.1063/1.5088248	journal	April 2019
Design and simulation of the snowflake divertor control for NSTX–U Vail, P. J.; Boyer, M. D.; Welander, A. S. Plasma Physics and Controlled Fusion, Vol. 61, Issue 3 https://doi.org/10.1088/1361-6587/aaf94a	journal	January 2019
Initial development of the DIII–D snowflake divertor control Kolemen, E.; Vail, P. J.; Makowski, M. A. Nuclear Fusion, Vol. 58, Issue 6 https://doi.org/10.1088/1741-4326/aab0d3	journal	April 2018
Divertor leg filaments in NSTX-U Scotti, Filippo; Zweben, Stewart; Soukhanovskii, Vlad Nuclear Fusion, Vol. 58, Issue 12 https://doi.org/10.1088/1741-4326/aae49f	journal	October 2018
Real-time capable modeling of neutral beam injection on NSTX-U using neural networks Boyer, M. D.; Kaye, S.; Erickson, K. Nuclear Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1741-4326/ab0762	journal	March 2019
Effect of sawtooth crashes on fast ion distribution in NSTX-U Liu, D.; Heidbrink, W. W.; Podestà, M. Nuclear Fusion, Vol. 58, Issue 8 https://doi.org/10.1088/1741-4326/aac64f	journal	July 2018

Similar Records

Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U

Dataset · Thu Mar 01 00:00:00 EST 2018 · OSTI ID:1419785

Boyer, M; Battaglia, D; Mueller, D; +12 more

Overview of the physics and engineering design of NSTX upgrade

Journal Article · Sun Jan 01 00:00:00 EST 2012 · Nuclear Fusion · OSTI ID:1419785

Menard, J. E.; Gerhardt, S. P.; Bell, M.; +5 more

Overview of NSTX Upgrade Initial Results and Modelling Highlights

Dataset · Sun Jan 01 00:00:00 EST 2017 · OSTI ID:1419785

Menard, J.E.; Allain, J.P.; Battaglia, D.J.; +96 more

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
spherical torus
plasma boundary control
plasma boundary reconstruction
MIMO feedback control

Title: Plasma boundary shape control and real-time equilibrium reconstruction on NSTX-U

Citation Formats

References (43)

Cited By (6)

Similar Records

Related Subjects