Progress toward fully noninductive, high beta conditions in DIII-D

M. Murakami; M. R. Wade; C. M. Greenfield; T. C. Luce; J. R. Ferron; H. E.St John; J. C. Deboo; W. W. Heidbrink; Y. Luo; M. A. Makowski; T. H. Osborne; C. C. Petty; P. A. Politzer; S. L. Allen; M. E. Austin; K. H. Burrell; T. A. Casper; E. J. Doyle; A. M. Garofalo; P. Gohil; I. A. Gorelov; R. J. Groebner; A. W. Hyatt; R. J. Jayakumar; K. Kajiwara; C. E. Kessel; J. E. Kinsey; R. J. La Haye; L. L. Lao; A. W. Leonard; J. Lohr; T. W. Petrie; R. I. Pinsker; R. Prater; T. L. Rhodes; A. C.C. Sips; G. M. Staebler; T. S. Taylor; M. A. Vanzeeland; G. Wang; W. P. West; L. Zeng

doi:10.1063/1.2173627

Progress toward fully noninductive, high beta conditions in DIII-D

M. Murakami, M. R. Wade, C. M. Greenfield, T. C. Luce, J. R. Ferron, H. E.St John, J. C. Deboo, W. W. Heidbrink, Y. Luo, M. A. Makowski, T. H. Osborne, C. C. Petty, P. A. Politzer, S. L. Allen, M. E. Austin, K. H. Burrell, T. A. Casper, E. J. Doyle, A. M. Garofalo, P. GohilI. A. Gorelov, R. J. Groebner, A. W. Hyatt, R. J. Jayakumar, K. Kajiwara, C. E. Kessel, J. E. Kinsey, R. J. La Haye, L. L. Lao, A. W. Leonard, J. Lohr, T. W. Petrie, R. I. Pinsker, R. Prater, T. L. Rhodes, A. C.C. Sips, G. M. Staebler, T. S. Taylor, M. A. Vanzeeland, G. Wang, W. P. West, L. Zeng

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Abstract

The DIII-D Advanced Tokamak (AT) program in the DIII-D tokamak [J. L. Luxon, Plasma Physics and Controlled Fusion Research, 1986, Vol. I (International Atomic Energy Agency, Vienna, 1987), p. 159] is aimed at developing a scientific basis for steady-state, high-performance operation in future devices. This requires simultaneously achieving 100% noninductive operation with high self-driven bootstrap current fraction and toroidal beta. Recent progress in this area includes demonstration of 100% noninductive conditions with toroidal beta, ΒT =3.6%, normalized beta, ΒN =3.5, and confinement factor, H89 =2.4 with the plasma current driven completely by bootstrap, neutral beam current drive, and electron cyclotron current drive (ECCD). The equilibrium reconstructions indicate that the noninductive current profile is well aligned, with little inductively driven current remaining anywhere in the plasma. The current balance calculation improved with beam ion redistribution that was supported by recent fast ion diagnostic measurements. The duration of this state is limited by pressure profile evolution, leading to magnetohydrodynamic (MHD) instabilities after about 1 s or half of a current relaxation time (τCR). Stationary conditions are maintained in similar discharges (∼90% noninductive), limited only by the 2 s duration (1 τCR) of the present ECCD systems. By discussing parametric scans in a global parameter and profile databases, the need for low density and high beta are identified to achieve full noninductive operation and good current drive alignment. These experiments achieve the necessary fusion performance and bootstrap fraction to extrapolate to the fusion gain, Q=5 steady-state scenario in the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, Fusion Energy Conference on Controlled Fusion and Plasma Physics, Sorrento, Italy (International Atomic Energy Agency, Vienna, 1987), paper IAEA-CN-77/OV-1]. The modeling tools that have been successfully employed to both plan and interpret the experiment are used to plan future DIII-D experiments with higher power and longer pulse ECCD and fast wave and co- and counterneutral beam injection in a pumped double-null configuration. The models predict our ability to control the current and pressure profiles to reach full noninductivity with increased beta, bootstrap fraction, and duration. The same modeling tools are applied to ITER, predicting favorable prospects for the success of the ITER steady-state scenario.

Original language	English
Article number	056106
Journal	Physics of Plasmas
Volume	13
Issue number	5
DOIs	https://doi.org/10.1063/1.2173627
State	Published - May 2006
Externally published	Yes

Funding

This work was supported by the U.S. Department of Energy under DE-AC05-00OR22725, DE-FC02-04ER54698, SC-G903402, W-7405-ENG-48, DE-FG03-97ER54415, DE-FG03-01ER54615, DE-FG02-89ER53297, DE-AC02-76CH03073, and DE-FG02-85ER53214. We would like to thank the DIII-D Team. We also wish to acknowledge useful discussions with Dr. C. Gormezano, Dr. W. A. Houlberg, and Dr. J. M. Park. Some of the modeling was carried out using Grid-enabled TRANSP on the National Fusion Grid, and we would like to thank the members of the National Fusion Collaboratory Project (www.fusiongrid.org) at PPPL and GA sponsored by the U.S. DOE SciDAC Program.

Funders	Funder number
National Fusion Collaboratory Project
National Fusion Grid
U.S. Department of Energy	DE-AC05-00OR22725, DE-FG03-01ER54615, DE-FG03-97ER54415, DE-AC02-76CH03073, DE-FC02-04ER54698, DE-FG02-85ER53214, SC-G903402, W-7405-ENG-48, DE-FG02-89ER53297
U.S. Department of Energy

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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Murakami, M., Wade, M. R., Greenfield, C. M., Luce, T. C., Ferron, J. R., John, H. E. S., Deboo, J. C., Heidbrink, W. W., Luo, Y., Makowski, M. A., Osborne, T. H., Petty, C. C., Politzer, P. A., Allen, S. L., Austin, M. E., Burrell, K. H., Casper, T. A., Doyle, E. J., Garofalo, A. M., ... Zeng, L. (2006). Progress toward fully noninductive, high beta conditions in DIII-D. Physics of Plasmas, 13(5), Article 056106. https://doi.org/10.1063/1.2173627

@article{0a7d5d3f83bc43a3afc3d22c0aa90e62,

title = "Progress toward fully noninductive, high beta conditions in DIII-D",

abstract = "The DIII-D Advanced Tokamak (AT) program in the DIII-D tokamak [J. L. Luxon, Plasma Physics and Controlled Fusion Research, 1986, Vol. I (International Atomic Energy Agency, Vienna, 1987), p. 159] is aimed at developing a scientific basis for steady-state, high-performance operation in future devices. This requires simultaneously achieving 100% noninductive operation with high self-driven bootstrap current fraction and toroidal beta. Recent progress in this area includes demonstration of 100% noninductive conditions with toroidal beta, ΒT =3.6%, normalized beta, ΒN =3.5, and confinement factor, H89 =2.4 with the plasma current driven completely by bootstrap, neutral beam current drive, and electron cyclotron current drive (ECCD). The equilibrium reconstructions indicate that the noninductive current profile is well aligned, with little inductively driven current remaining anywhere in the plasma. The current balance calculation improved with beam ion redistribution that was supported by recent fast ion diagnostic measurements. The duration of this state is limited by pressure profile evolution, leading to magnetohydrodynamic (MHD) instabilities after about 1 s or half of a current relaxation time (τCR). Stationary conditions are maintained in similar discharges (∼90% noninductive), limited only by the 2 s duration (1 τCR) of the present ECCD systems. By discussing parametric scans in a global parameter and profile databases, the need for low density and high beta are identified to achieve full noninductive operation and good current drive alignment. These experiments achieve the necessary fusion performance and bootstrap fraction to extrapolate to the fusion gain, Q=5 steady-state scenario in the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, Fusion Energy Conference on Controlled Fusion and Plasma Physics, Sorrento, Italy (International Atomic Energy Agency, Vienna, 1987), paper IAEA-CN-77/OV-1]. The modeling tools that have been successfully employed to both plan and interpret the experiment are used to plan future DIII-D experiments with higher power and longer pulse ECCD and fast wave and co- and counterneutral beam injection in a pumped double-null configuration. The models predict our ability to control the current and pressure profiles to reach full noninductivity with increased beta, bootstrap fraction, and duration. The same modeling tools are applied to ITER, predicting favorable prospects for the success of the ITER steady-state scenario.",

author = "M. Murakami and Wade, {M. R.} and Greenfield, {C. M.} and Luce, {T. C.} and Ferron, {J. R.} and John, {H. E.St} and Deboo, {J. C.} and Heidbrink, {W. W.} and Y. Luo and Makowski, {M. A.} and Osborne, {T. H.} and Petty, {C. C.} and Politzer, {P. A.} and Allen, {S. L.} and Austin, {M. E.} and Burrell, {K. H.} and Casper, {T. A.} and Doyle, {E. J.} and Garofalo, {A. M.} and P. Gohil and Gorelov, {I. A.} and Groebner, {R. J.} and Hyatt, {A. W.} and Jayakumar, {R. J.} and K. Kajiwara and Kessel, {C. E.} and Kinsey, {J. E.} and {La Haye}, {R. J.} and Lao, {L. L.} and Leonard, {A. W.} and J. Lohr and Petrie, {T. W.} and Pinsker, {R. I.} and R. Prater and Rhodes, {T. L.} and Sips, {A. C.C.} and Staebler, {G. M.} and Taylor, {T. S.} and Vanzeeland, {M. A.} and G. Wang and West, {W. P.} and L. Zeng",

year = "2006",

month = may,

doi = "10.1063/1.2173627",

language = "English",

volume = "13",

journal = "Physics of Plasmas",

issn = "1070-664X",

publisher = "American Institute of Physics",

number = "5",

}

Murakami, M, Wade, MR , Greenfield, CM, Luce, TC, Ferron, JR, John, HES, Deboo, JC, Heidbrink, WW, Luo, Y, Makowski, MA, Osborne, TH, Petty, CC, Politzer, PA, Allen, SL, Austin, ME, Burrell, KH, Casper, TA, Doyle, EJ, Garofalo, AM, Gohil, P, Gorelov, IA, Groebner, RJ, Hyatt, AW, Jayakumar, RJ, Kajiwara, K, Kessel, CE, Kinsey, JE, La Haye, RJ, Lao, LL, Leonard, AW, Lohr, J, Petrie, TW, Pinsker, RI, Prater, R, Rhodes, TL, Sips, ACC, Staebler, GM, Taylor, TS, Vanzeeland, MA, Wang, G, West, WP & Zeng, L 2006, 'Progress toward fully noninductive, high beta conditions in DIII-D', Physics of Plasmas, vol. 13, no. 5, 056106. https://doi.org/10.1063/1.2173627

TY - JOUR

T1 - Progress toward fully noninductive, high beta conditions in DIII-D

AU - Murakami, M.

AU - Wade, M. R.

AU - Greenfield, C. M.

AU - Luce, T. C.

AU - Ferron, J. R.

AU - John, H. E.St

AU - Deboo, J. C.

AU - Heidbrink, W. W.

AU - Luo, Y.

AU - Makowski, M. A.

AU - Osborne, T. H.

AU - Petty, C. C.

AU - Politzer, P. A.

AU - Allen, S. L.

AU - Austin, M. E.

AU - Burrell, K. H.

AU - Casper, T. A.

AU - Doyle, E. J.

AU - Garofalo, A. M.

AU - Gohil, P.

AU - Gorelov, I. A.

AU - Groebner, R. J.

AU - Hyatt, A. W.

AU - Jayakumar, R. J.

AU - Kajiwara, K.

AU - Kessel, C. E.

AU - Kinsey, J. E.

AU - La Haye, R. J.

AU - Lao, L. L.

AU - Leonard, A. W.

AU - Lohr, J.

AU - Petrie, T. W.

AU - Pinsker, R. I.

AU - Prater, R.

AU - Rhodes, T. L.

AU - Sips, A. C.C.

AU - Staebler, G. M.

AU - Taylor, T. S.

AU - Vanzeeland, M. A.

AU - Wang, G.

AU - West, W. P.

AU - Zeng, L.

PY - 2006/5

Y1 - 2006/5

N2 - The DIII-D Advanced Tokamak (AT) program in the DIII-D tokamak [J. L. Luxon, Plasma Physics and Controlled Fusion Research, 1986, Vol. I (International Atomic Energy Agency, Vienna, 1987), p. 159] is aimed at developing a scientific basis for steady-state, high-performance operation in future devices. This requires simultaneously achieving 100% noninductive operation with high self-driven bootstrap current fraction and toroidal beta. Recent progress in this area includes demonstration of 100% noninductive conditions with toroidal beta, ΒT =3.6%, normalized beta, ΒN =3.5, and confinement factor, H89 =2.4 with the plasma current driven completely by bootstrap, neutral beam current drive, and electron cyclotron current drive (ECCD). The equilibrium reconstructions indicate that the noninductive current profile is well aligned, with little inductively driven current remaining anywhere in the plasma. The current balance calculation improved with beam ion redistribution that was supported by recent fast ion diagnostic measurements. The duration of this state is limited by pressure profile evolution, leading to magnetohydrodynamic (MHD) instabilities after about 1 s or half of a current relaxation time (τCR). Stationary conditions are maintained in similar discharges (∼90% noninductive), limited only by the 2 s duration (1 τCR) of the present ECCD systems. By discussing parametric scans in a global parameter and profile databases, the need for low density and high beta are identified to achieve full noninductive operation and good current drive alignment. These experiments achieve the necessary fusion performance and bootstrap fraction to extrapolate to the fusion gain, Q=5 steady-state scenario in the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, Fusion Energy Conference on Controlled Fusion and Plasma Physics, Sorrento, Italy (International Atomic Energy Agency, Vienna, 1987), paper IAEA-CN-77/OV-1]. The modeling tools that have been successfully employed to both plan and interpret the experiment are used to plan future DIII-D experiments with higher power and longer pulse ECCD and fast wave and co- and counterneutral beam injection in a pumped double-null configuration. The models predict our ability to control the current and pressure profiles to reach full noninductivity with increased beta, bootstrap fraction, and duration. The same modeling tools are applied to ITER, predicting favorable prospects for the success of the ITER steady-state scenario.

AB - The DIII-D Advanced Tokamak (AT) program in the DIII-D tokamak [J. L. Luxon, Plasma Physics and Controlled Fusion Research, 1986, Vol. I (International Atomic Energy Agency, Vienna, 1987), p. 159] is aimed at developing a scientific basis for steady-state, high-performance operation in future devices. This requires simultaneously achieving 100% noninductive operation with high self-driven bootstrap current fraction and toroidal beta. Recent progress in this area includes demonstration of 100% noninductive conditions with toroidal beta, ΒT =3.6%, normalized beta, ΒN =3.5, and confinement factor, H89 =2.4 with the plasma current driven completely by bootstrap, neutral beam current drive, and electron cyclotron current drive (ECCD). The equilibrium reconstructions indicate that the noninductive current profile is well aligned, with little inductively driven current remaining anywhere in the plasma. The current balance calculation improved with beam ion redistribution that was supported by recent fast ion diagnostic measurements. The duration of this state is limited by pressure profile evolution, leading to magnetohydrodynamic (MHD) instabilities after about 1 s or half of a current relaxation time (τCR). Stationary conditions are maintained in similar discharges (∼90% noninductive), limited only by the 2 s duration (1 τCR) of the present ECCD systems. By discussing parametric scans in a global parameter and profile databases, the need for low density and high beta are identified to achieve full noninductive operation and good current drive alignment. These experiments achieve the necessary fusion performance and bootstrap fraction to extrapolate to the fusion gain, Q=5 steady-state scenario in the International Thermonuclear Experimental Reactor (ITER) [R. Aymar, Fusion Energy Conference on Controlled Fusion and Plasma Physics, Sorrento, Italy (International Atomic Energy Agency, Vienna, 1987), paper IAEA-CN-77/OV-1]. The modeling tools that have been successfully employed to both plan and interpret the experiment are used to plan future DIII-D experiments with higher power and longer pulse ECCD and fast wave and co- and counterneutral beam injection in a pumped double-null configuration. The models predict our ability to control the current and pressure profiles to reach full noninductivity with increased beta, bootstrap fraction, and duration. The same modeling tools are applied to ITER, predicting favorable prospects for the success of the ITER steady-state scenario.

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U2 - 10.1063/1.2173627

DO - 10.1063/1.2173627

M3 - Article

AN - SCOPUS:33744788877

SN - 1070-664X

VL - 13

JO - Physics of Plasmas

JF - Physics of Plasmas

IS - 5

M1 - 056106

ER -

Progress toward fully noninductive, high beta conditions in DIII-D

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