Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade

G. Taylor; F. Poli; N. Bertelli; R. W. Harvey; J. C. Hosea; D. Mueller; R. J. Perkins; C. K. Phillips; R. Raman

doi:10.1063/1.4936487

Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade

G. Taylor, F. Poli, N. Bertelli, R. W. Harvey, J. C. Hosea, D. Mueller, R. J. Perkins, C. K. Phillips, R. Raman

PPPL NSTX

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Abstract

A major challenge for spherical tokamak development is to start-up and ramp-up the plasma current (I_p) without using a central solenoid. Experiments in the National Spherical Torus eXperiment (NSTX) demonstrated that 1.4 MW of 30 MHz high-harmonic fast wave (HHFW) power could generate an I_p = 300 kA H-mode discharge with a non-inductive I_p fraction, f_NI ∼ 0.7. The discharge had an axial toroidal magnetic field (B_T(0)) of 0.55 T, the maximum B_T(0) available on NSTX. NSTX has undergone a major upgrade (NSTX-U), that will eventually allow the generation of B_T(0) ≤ 1 T and I_p ≤ 2 MA plasmas. Full wave simulations of 30 MHz HHFW and medium harmonic fast wave (MHFW) heating in NSTX-U predict significantly reduced FW power loss in the plasma edge at the higher B_T(0) achievable in NSTX-U. HHFW experiments will aim to generate stable, f_NI ∼ 1, I_p = 300 kA H-mode plasmas and to ramp I_p from 250 to 400 kA with FW power. Time-dependent TRANSP simulations are used to develop non-inductive Ip ramp-up and sustainment using 30 MHz FW power. This paper presents results from these RF simulations and plans for developing non-inductive plasmas heated by FW power.

Original language	English (US)
Title of host publication	Radio Frequency Power in Plasmas
Subtitle of host publication	Proceedings of the 21St Topical Conference
Editors	Robert I. Pinsker
Publisher	American Institute of Physics Inc.
ISBN (Electronic)	9780735413368
DOIs	https://doi.org/10.1063/1.4936487
State	Published - Dec 10 2015
Event	21st Topical Conference on Radiofrequency Power in Plasmas - Lake Arrowhead, United States Duration: Apr 27 2015 → Apr 29 2015

Publication series

Name	AIP Conference Proceedings
Volume	1689
ISSN (Print)	0094-243X
ISSN (Electronic)	1551-7616

Other

Other	21st Topical Conference on Radiofrequency Power in Plasmas
Country/Territory	United States
City	Lake Arrowhead
Period	4/27/15 → 4/29/15

All Science Journal Classification (ASJC) codes

General Physics and Astronomy

Access to Document

10.1063/1.4936487

Cite this

Taylor, G., Poli, F., Bertelli, N., Harvey, R. W., Hosea, J. C., Mueller, D., Perkins, R. J., Phillips, C. K., & Raman, R. (2015). Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade. In R. I. Pinsker (Ed.), Radio Frequency Power in Plasmas: Proceedings of the 21St Topical Conference Article 040004 (AIP Conference Proceedings; Vol. 1689). American Institute of Physics Inc.. https://doi.org/10.1063/1.4936487

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title = "Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade",

abstract = "A major challenge for spherical tokamak development is to start-up and ramp-up the plasma current (Ip) without using a central solenoid. Experiments in the National Spherical Torus eXperiment (NSTX) demonstrated that 1.4 MW of 30 MHz high-harmonic fast wave (HHFW) power could generate an Ip = 300 kA H-mode discharge with a non-inductive Ip fraction, fNI ∼ 0.7. The discharge had an axial toroidal magnetic field (BT(0)) of 0.55 T, the maximum BT(0) available on NSTX. NSTX has undergone a major upgrade (NSTX-U), that will eventually allow the generation of BT(0) ≤ 1 T and Ip ≤ 2 MA plasmas. Full wave simulations of 30 MHz HHFW and medium harmonic fast wave (MHFW) heating in NSTX-U predict significantly reduced FW power loss in the plasma edge at the higher BT(0) achievable in NSTX-U. HHFW experiments will aim to generate stable, fNI ∼ 1, Ip = 300 kA H-mode plasmas and to ramp Ip from 250 to 400 kA with FW power. Time-dependent TRANSP simulations are used to develop non-inductive Ip ramp-up and sustainment using 30 MHz FW power. This paper presents results from these RF simulations and plans for developing non-inductive plasmas heated by FW power.",

author = "G. Taylor and F. Poli and N. Bertelli and Harvey, \{R. W.\} and Hosea, \{J. C.\} and D. Mueller and Perkins, \{R. J.\} and Phillips, \{C. K.\} and R. Raman",

note = "Publisher Copyright: {\textcopyright} 2015 AIP Publishing LLC.; 21st Topical Conference on Radiofrequency Power in Plasmas ; Conference date: 27-04-2015 Through 29-04-2015",

year = "2015",

month = dec,

day = "10",

doi = "10.1063/1.4936487",

language = "English (US)",

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Taylor, G, Poli, F, Bertelli, N, Harvey, RW, Hosea, JC, Mueller, D, Perkins, RJ, Phillips, CK & Raman, R 2015, Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade. in RI Pinsker (ed.), Radio Frequency Power in Plasmas: Proceedings of the 21St Topical Conference., 040004, AIP Conference Proceedings, vol. 1689, American Institute of Physics Inc., 21st Topical Conference on Radiofrequency Power in Plasmas, Lake Arrowhead, United States, 4/27/15. https://doi.org/10.1063/1.4936487

Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade. / Taylor, G.; Poli, F.; Bertelli, N. et al.
Radio Frequency Power in Plasmas: Proceedings of the 21St Topical Conference. ed. / Robert I. Pinsker. American Institute of Physics Inc., 2015. 040004 (AIP Conference Proceedings; Vol. 1689).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

TY - GEN

T1 - Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade

AU - Taylor, G.

AU - Poli, F.

AU - Bertelli, N.

AU - Harvey, R. W.

AU - Hosea, J. C.

AU - Mueller, D.

AU - Perkins, R. J.

AU - Phillips, C. K.

AU - Raman, R.

PY - 2015/12/10

Y1 - 2015/12/10

N2 - A major challenge for spherical tokamak development is to start-up and ramp-up the plasma current (Ip) without using a central solenoid. Experiments in the National Spherical Torus eXperiment (NSTX) demonstrated that 1.4 MW of 30 MHz high-harmonic fast wave (HHFW) power could generate an Ip = 300 kA H-mode discharge with a non-inductive Ip fraction, fNI ∼ 0.7. The discharge had an axial toroidal magnetic field (BT(0)) of 0.55 T, the maximum BT(0) available on NSTX. NSTX has undergone a major upgrade (NSTX-U), that will eventually allow the generation of BT(0) ≤ 1 T and Ip ≤ 2 MA plasmas. Full wave simulations of 30 MHz HHFW and medium harmonic fast wave (MHFW) heating in NSTX-U predict significantly reduced FW power loss in the plasma edge at the higher BT(0) achievable in NSTX-U. HHFW experiments will aim to generate stable, fNI ∼ 1, Ip = 300 kA H-mode plasmas and to ramp Ip from 250 to 400 kA with FW power. Time-dependent TRANSP simulations are used to develop non-inductive Ip ramp-up and sustainment using 30 MHz FW power. This paper presents results from these RF simulations and plans for developing non-inductive plasmas heated by FW power.

AB - A major challenge for spherical tokamak development is to start-up and ramp-up the plasma current (Ip) without using a central solenoid. Experiments in the National Spherical Torus eXperiment (NSTX) demonstrated that 1.4 MW of 30 MHz high-harmonic fast wave (HHFW) power could generate an Ip = 300 kA H-mode discharge with a non-inductive Ip fraction, fNI ∼ 0.7. The discharge had an axial toroidal magnetic field (BT(0)) of 0.55 T, the maximum BT(0) available on NSTX. NSTX has undergone a major upgrade (NSTX-U), that will eventually allow the generation of BT(0) ≤ 1 T and Ip ≤ 2 MA plasmas. Full wave simulations of 30 MHz HHFW and medium harmonic fast wave (MHFW) heating in NSTX-U predict significantly reduced FW power loss in the plasma edge at the higher BT(0) achievable in NSTX-U. HHFW experiments will aim to generate stable, fNI ∼ 1, Ip = 300 kA H-mode plasmas and to ramp Ip from 250 to 400 kA with FW power. Time-dependent TRANSP simulations are used to develop non-inductive Ip ramp-up and sustainment using 30 MHz FW power. This paper presents results from these RF simulations and plans for developing non-inductive plasmas heated by FW power.

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M3 - Conference contribution

AN - SCOPUS:84984586107

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BT - Radio Frequency Power in Plasmas

A2 - Pinsker, Robert I.

PB - American Institute of Physics Inc.

T2 - 21st Topical Conference on Radiofrequency Power in Plasmas

Y2 - 27 April 2015 through 29 April 2015

ER -

Taylor G, Poli F, Bertelli N, Harvey RW, Hosea JC, Mueller D et al. Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade. In Pinsker RI, editor, Radio Frequency Power in Plasmas: Proceedings of the 21St Topical Conference. American Institute of Physics Inc. 2015. 040004. (AIP Conference Proceedings). doi: 10.1063/1.4936487

Development of fully non-inductive plasmas heated by medium and high-harmonic fast waves in the national spherical torus experiment upgrade

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