Results of NSTX heating experiments

D. Mueller; M. Ono; M. G. Bell; R. E. Bell; M. Bitter; C. Bourdelle; D. S. Darrow; P. C. Efthimion; E. D. Fredrickson; D. A. Gates; Robert James Goldston; L. R. Grisham; R. J. Hawryluk; K. W. Hill; J. C. Hosea; S. C. Jardin; Hantao Ji; S. M. Kaye; R. Kaita; H. W. Kugel; D. W. Johnson; B. P. LeBlanc; R. Majeski; E. Mazzucato; S. S. Medley; J. E. Menard; H. K. Park; S. F. Paul; C. K. Phillips; M. H. Redi; A. L. Rosenberg; C. H. Skinner; V. A. Soukhanovskii; B. Stratton; E. J. Synakowski; G. Taylor; J. R. Wilson; S. J. Zweben; W. D. Dorland; Y. K.M. Peng; R. Barry; T. Bigelow; C. E. Bush; M. Carter; R. Maingi; M. Menon; P. M. Ryan; D. W. Swain; J. Wilgen; S. A. Sabbagh; F. Paoletti; J. Bialek; W. Zhu; R. Raman; T. R. Jarboe; B. A. Nelson; R. J. Maqueda; G. A. Wurden; R. I. Pinsker; M. Schaffer; J. Ferron; L. Lao; D. Stutman; M. Finkenthal; W. Wampler; S. Kubota; W. A. Peebles; M. Gilmore; T. K. Mau; K. C. Lee; C. W. Domier; B. H. Deng; M. Johnson; N. C. Luhmann; P. Bonoli; A. Bers; A. Ram; R. Akers; Y. Takase; A. Ejiri; Y. Ono; S. Shiraiwa; N. Nishino; O. Mitarai; M. Nagata; J. G. Yang; H. Na; D. Pacella

doi:10.1109/TPS.2003.808890

Results of NSTX heating experiments

D. Mueller, M. Ono, M. G. Bell, R. E. Bell, M. Bitter, C. Bourdelle, D. S. Darrow, P. C. Efthimion, E. D. Fredrickson, D. A. Gates, Robert James Goldston, L. R. Grisham, R. J. Hawryluk, K. W. Hill, J. C. Hosea, S. C. Jardin, Hantao Ji, S. M. Kaye, R. Kaita, H. W. KugelD. W. Johnson, B. P. LeBlanc, R. Majeski, E. Mazzucato, S. S. Medley, J. E. Menard, H. K. Park, S. F. Paul, C. K. Phillips, M. H. Redi, A. L. Rosenberg, C. H. Skinner, V. A. Soukhanovskii, B. Stratton, E. J. Synakowski, G. Taylor, J. R. Wilson, S. J. Zweben, W. D. Dorland, Y. K.M. Peng, R. Barry, T. Bigelow, C. E. Bush, M. Carter, R. Maingi, M. Menon, P. M. Ryan, D. W. Swain, J. Wilgen, S. A. Sabbagh, F. Paoletti, J. Bialek, W. Zhu, R. Raman, T. R. Jarboe, B. A. Nelson, R. J. Maqueda, G. A. Wurden, R. I. Pinsker, M. Schaffer, J. Ferron, L. Lao, D. Stutman, M. Finkenthal, W. Wampler, S. Kubota, W. A. Peebles, M. Gilmore, T. K. Mau, K. C. Lee, C. W. Domier, B. H. Deng, M. Johnson, N. C. Luhmann, P. Bonoli, A. Bers, A. Ram, R. Akers, Y. Takase, A. Ejiri, Y. Ono, S. Shiraiwa, N. Nishino, O. Mitarai, M. Nagata, J. G. Yang, H. Na, D. Pacella

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Abstract

The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave (HHFW) at 30 MHz. NSTX has achieved β_T of 32%. A variety of MHD phenomena have been observed to limit β. NSTX has now begun addressing τ_E scaling, β limits, and current drive Issues. During the NBI heating experiments, a broad T_i profile with T_i up to 2 keV, T_i > T_e anda large toroidal rotation were observed. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, τ_E is up to two times the ITER97L L-Mode scaling and exceeds the ITER98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of τ_E after the transition in some conditions. During HHFW heating, T_e > T_i and T_e up to 3.5 keV were observed. Current drive has been studied using both coaxial helicity injection with up to 390 kA of toroidal current and HHFW. HHFW has produced H-modes with significant bootstrap current fraction at low I_p, high q, and high β_p.

Original language	English (US)
Pages (from-to)	60-67
Number of pages	8
Journal	IEEE Transactions on Plasma Science
Volume	31
Issue number	1 I
DOIs	https://doi.org/10.1109/TPS.2003.808890
State	Published - Feb 2003

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

Keywords

Fusion reactors
Plasma confinement
Tokamaks

Access to Document

10.1109/TPS.2003.808890

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Mueller, D., Ono, M., Bell, M. G., Bell, R. E., Bitter, M., Bourdelle, C., Darrow, D. S., Efthimion, P. C., Fredrickson, E. D., Gates, D. A., Goldston, R. J., Grisham, L. R., Hawryluk, R. J., Hill, K. W., Hosea, J. C., Jardin, S. C., Ji, H., Kaye, S. M., Kaita, R., ... Pacella, D. (2003). Results of NSTX heating experiments. IEEE Transactions on Plasma Science, 31(1 I), 60-67. https://doi.org/10.1109/TPS.2003.808890

@article{f49e949383d046e2b9b87e8d7cac1aa0,

title = "Results of NSTX heating experiments",

abstract = "The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave (HHFW) at 30 MHz. NSTX has achieved βT of 32%. A variety of MHD phenomena have been observed to limit β. NSTX has now begun addressing τE scaling, β limits, and current drive Issues. During the NBI heating experiments, a broad Ti profile with Ti up to 2 keV, Ti > Te anda large toroidal rotation were observed. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, τE is up to two times the ITER97L L-Mode scaling and exceeds the ITER98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of τE after the transition in some conditions. During HHFW heating, Te > Ti and Te up to 3.5 keV were observed. Current drive has been studied using both coaxial helicity injection with up to 390 kA of toroidal current and HHFW. HHFW has produced H-modes with significant bootstrap current fraction at low Ip, high q, and high βp.",

keywords = "Fusion reactors, Plasma confinement, Tokamaks",

author = "D. Mueller and M. Ono and Bell, {M. G.} and Bell, {R. E.} and M. Bitter and C. Bourdelle and Darrow, {D. S.} and Efthimion, {P. C.} and Fredrickson, {E. D.} and Gates, {D. A.} and Goldston, {Robert James} and Grisham, {L. R.} and Hawryluk, {R. J.} and Hill, {K. W.} and Hosea, {J. C.} and Jardin, {S. C.} and Hantao Ji and Kaye, {S. M.} and R. Kaita and Kugel, {H. W.} and Johnson, {D. W.} and LeBlanc, {B. P.} and R. Majeski and E. Mazzucato and Medley, {S. S.} and Menard, {J. E.} and Park, {H. K.} and Paul, {S. F.} and Phillips, {C. K.} and Redi, {M. H.} and Rosenberg, {A. L.} and Skinner, {C. H.} and Soukhanovskii, {V. A.} and B. Stratton and Synakowski, {E. J.} and G. Taylor and Wilson, {J. R.} and Zweben, {S. J.} and Dorland, {W. D.} and Peng, {Y. K.M.} and R. Barry and T. Bigelow and Bush, {C. E.} and M. Carter and R. Maingi and M. Menon and Ryan, {P. M.} and Swain, {D. W.} and J. Wilgen and Sabbagh, {S. A.} and F. Paoletti and J. Bialek and W. Zhu and R. Raman and Jarboe, {T. R.} and Nelson, {B. A.} and Maqueda, {R. J.} and Wurden, {G. A.} and Pinsker, {R. I.} and M. Schaffer and J. Ferron and L. Lao and D. Stutman and M. Finkenthal and W. Wampler and S. Kubota and Peebles, {W. A.} and M. Gilmore and Mau, {T. K.} and Lee, {K. C.} and Domier, {C. W.} and Deng, {B. H.} and M. Johnson and Luhmann, {N. C.} and P. Bonoli and A. Bers and A. Ram and R. Akers and Y. Takase and A. Ejiri and Y. Ono and S. Shiraiwa and N. Nishino and O. Mitarai and M. Nagata and Yang, {J. G.} and H. Na and D. Pacella",

note = "Funding Information: Manuscript received June 14, 2002; revised November 4, 2002. This work was supported in part by the U.S. Department of Energy under contract DE-AC02-76CH030.",

year = "2003",

month = feb,

doi = "10.1109/TPS.2003.808890",

language = "English (US)",

volume = "31",

pages = "60--67",

journal = "IEEE Transactions on Plasma Science",

issn = "0093-3813",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

number = "1 I",

}

Mueller, D, Ono, M, Bell, MG, Bell, RE, Bitter, M, Bourdelle, C, Darrow, DS, Efthimion, PC, Fredrickson, ED, Gates, DA, Goldston, RJ, Grisham, LR, Hawryluk, RJ, Hill, KW, Hosea, JC, Jardin, SC, Ji, H, Kaye, SM, Kaita, R, Kugel, HW, Johnson, DW, LeBlanc, BP, Majeski, R, Mazzucato, E, Medley, SS, Menard, JE, Park, HK, Paul, SF, Phillips, CK, Redi, MH, Rosenberg, AL, Skinner, CH, Soukhanovskii, VA, Stratton, B, Synakowski, EJ, Taylor, G, Wilson, JR, Zweben, SJ, Dorland, WD, Peng, YKM, Barry, R, Bigelow, T, Bush, CE, Carter, M, Maingi, R, Menon, M, Ryan, PM, Swain, DW, Wilgen, J, Sabbagh, SA, Paoletti, F, Bialek, J, Zhu, W, Raman, R, Jarboe, TR, Nelson, BA, Maqueda, RJ, Wurden, GA, Pinsker, RI, Schaffer, M, Ferron, J, Lao, L, Stutman, D, Finkenthal, M, Wampler, W, Kubota, S, Peebles, WA, Gilmore, M, Mau, TK, Lee, KC, Domier, CW, Deng, BH, Johnson, M, Luhmann, NC, Bonoli, P, Bers, A, Ram, A, Akers, R, Takase, Y, Ejiri, A, Ono, Y, Shiraiwa, S, Nishino, N, Mitarai, O, Nagata, M, Yang, JG, Na, H & Pacella, D 2003, 'Results of NSTX heating experiments', IEEE Transactions on Plasma Science, vol. 31, no. 1 I, pp. 60-67. https://doi.org/10.1109/TPS.2003.808890

TY - JOUR

T1 - Results of NSTX heating experiments

AU - Mueller, D.

AU - Ono, M.

AU - Bell, M. G.

AU - Bell, R. E.

AU - Bitter, M.

AU - Bourdelle, C.

AU - Darrow, D. S.

AU - Efthimion, P. C.

AU - Fredrickson, E. D.

AU - Gates, D. A.

AU - Goldston, Robert James

AU - Grisham, L. R.

AU - Hawryluk, R. J.

AU - Hill, K. W.

AU - Hosea, J. C.

AU - Jardin, S. C.

AU - Ji, Hantao

AU - Kaye, S. M.

AU - Kaita, R.

AU - Kugel, H. W.

AU - Johnson, D. W.

AU - LeBlanc, B. P.

AU - Majeski, R.

AU - Mazzucato, E.

AU - Medley, S. S.

AU - Menard, J. E.

AU - Park, H. K.

AU - Paul, S. F.

AU - Phillips, C. K.

AU - Redi, M. H.

AU - Rosenberg, A. L.

AU - Skinner, C. H.

AU - Soukhanovskii, V. A.

AU - Stratton, B.

AU - Synakowski, E. J.

AU - Taylor, G.

AU - Wilson, J. R.

AU - Zweben, S. J.

AU - Dorland, W. D.

AU - Peng, Y. K.M.

AU - Barry, R.

AU - Bigelow, T.

AU - Bush, C. E.

AU - Carter, M.

AU - Maingi, R.

AU - Menon, M.

AU - Ryan, P. M.

AU - Swain, D. W.

AU - Wilgen, J.

AU - Sabbagh, S. A.

AU - Paoletti, F.

AU - Bialek, J.

AU - Zhu, W.

AU - Raman, R.

AU - Jarboe, T. R.

AU - Nelson, B. A.

AU - Maqueda, R. J.

AU - Wurden, G. A.

AU - Pinsker, R. I.

AU - Schaffer, M.

AU - Ferron, J.

AU - Lao, L.

AU - Stutman, D.

AU - Finkenthal, M.

AU - Wampler, W.

AU - Kubota, S.

AU - Peebles, W. A.

AU - Gilmore, M.

AU - Mau, T. K.

AU - Lee, K. C.

AU - Domier, C. W.

AU - Deng, B. H.

AU - Johnson, M.

AU - Luhmann, N. C.

AU - Bonoli, P.

AU - Bers, A.

AU - Ram, A.

AU - Akers, R.

AU - Takase, Y.

AU - Ejiri, A.

AU - Ono, Y.

AU - Shiraiwa, S.

AU - Nishino, N.

AU - Mitarai, O.

AU - Nagata, M.

AU - Yang, J. G.

AU - Na, H.

AU - Pacella, D.

N1 - Funding Information: Manuscript received June 14, 2002; revised November 4, 2002. This work was supported in part by the U.S. Department of Energy under contract DE-AC02-76CH030.

PY - 2003/2

Y1 - 2003/2

N2 - The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave (HHFW) at 30 MHz. NSTX has achieved βT of 32%. A variety of MHD phenomena have been observed to limit β. NSTX has now begun addressing τE scaling, β limits, and current drive Issues. During the NBI heating experiments, a broad Ti profile with Ti up to 2 keV, Ti > Te anda large toroidal rotation were observed. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, τE is up to two times the ITER97L L-Mode scaling and exceeds the ITER98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of τE after the transition in some conditions. During HHFW heating, Te > Ti and Te up to 3.5 keV were observed. Current drive has been studied using both coaxial helicity injection with up to 390 kA of toroidal current and HHFW. HHFW has produced H-modes with significant bootstrap current fraction at low Ip, high q, and high βp.

AB - The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave (HHFW) at 30 MHz. NSTX has achieved βT of 32%. A variety of MHD phenomena have been observed to limit β. NSTX has now begun addressing τE scaling, β limits, and current drive Issues. During the NBI heating experiments, a broad Ti profile with Ti up to 2 keV, Ti > Te anda large toroidal rotation were observed. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, τE is up to two times the ITER97L L-Mode scaling and exceeds the ITER98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of τE after the transition in some conditions. During HHFW heating, Te > Ti and Te up to 3.5 keV were observed. Current drive has been studied using both coaxial helicity injection with up to 390 kA of toroidal current and HHFW. HHFW has produced H-modes with significant bootstrap current fraction at low Ip, high q, and high βp.

KW - Fusion reactors

KW - Plasma confinement

KW - Tokamaks

UR - http://www.scopus.com/inward/record.url?scp=0037308765&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0037308765&partnerID=8YFLogxK

U2 - 10.1109/TPS.2003.808890

DO - 10.1109/TPS.2003.808890

M3 - Article

AN - SCOPUS:0037308765

SN - 0093-3813

VL - 31

SP - 60

EP - 67

JO - IEEE Transactions on Plasma Science

JF - IEEE Transactions on Plasma Science

IS - 1 I

ER -

Results of NSTX heating experiments

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