Ohmic flux consumption during initial operation of the NSTX spherical torus

J. E. Menard; B. P. LeBlanc; S. A. Sabbagh; M. G. Bell; R. E. Bell; E. D. Fredrickson; D. A. Gates; S. C. Jardin; D. W. Johnson; S. M. Kaye; H. W. Kugel; R. Maingi; R. J. Maqueda; D. Mueller; M. Ono; F. Paoletti; S. F. Paul; C. H. Skinnera; D. Stutman

doi:10.1088/0029-5515/41/9/308

Ohmic flux consumption during initial operation of the NSTX spherical torus

J. E. Menard
, B. P. LeBlanc
, S. A. Sabbagh
, M. G. Bell
, R. E. Bell
, E. D. Fredrickson
, D. A. Gates
, S. C. Jardin
, D. W. Johnson
, S. M. Kaye
, H. W. Kugel
, R. Maingi
, R. J. Maqueda
, D. Mueller
, M. Ono
, F. Paoletti
, S. F. Paul
, C. H. Skinnera
, D. Stutman

Research output: Contribution to journal › Article › peer-review

28 Scopus citations

Abstract

Spherical tokamaks, because of their slender central columns, have very limited volt second capability relative to that of standard aspect ratio tokamaks of similar plasma cross-section. Recent experiments on NSTX have begun to quantify and optimize the ohmic current drive efficiency in an MA class ST device. Sustainable ramp rates in excess of 5 MA/s during the current rise phase have been achieved on NSTX, while faster ramps generate significant MHD activity. Discharges with I_p exceeding 1 MA have been achieved in NSTX with nominal parameters: aspect ratio A = 1.3-1.4, elongation κ = 2-2.2, triangularity δ = 0.4, internal inductance l_i = 0.6, Ejima coefficient C_E = 0.35. Flux consumption efficiency results, performance improvements associated with first boronization and comparisons with neoclassical resistivity are described.

Original language	English (US)
Pages (from-to)	1197-1206
Number of pages	10
Journal	Nuclear Fusion
Volume	41
Issue number	9
DOIs	https://doi.org/10.1088/0029-5515/41/9/308
State	Published - Sep 2001

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

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Menard, J. E., LeBlanc, B. P., Sabbagh, S. A., Bell, M. G., Bell, R. E., Fredrickson, E. D., Gates, D. A., Jardin, S. C., Johnson, D. W., Kaye, S. M., Kugel, H. W., Maingi, R., Maqueda, R. J., Mueller, D., Ono, M., Paoletti, F., Paul, S. F., Skinnera, C. H., & Stutman, D. (2001). Ohmic flux consumption during initial operation of the NSTX spherical torus. Nuclear Fusion, 41(9), 1197-1206. https://doi.org/10.1088/0029-5515/41/9/308

@article{57060ce03a46452987e978cbf06707ab,

title = "Ohmic flux consumption during initial operation of the NSTX spherical torus",

abstract = "Spherical tokamaks, because of their slender central columns, have very limited volt second capability relative to that of standard aspect ratio tokamaks of similar plasma cross-section. Recent experiments on NSTX have begun to quantify and optimize the ohmic current drive efficiency in an MA class ST device. Sustainable ramp rates in excess of 5 MA/s during the current rise phase have been achieved on NSTX, while faster ramps generate significant MHD activity. Discharges with Ip exceeding 1 MA have been achieved in NSTX with nominal parameters: aspect ratio A = 1.3-1.4, elongation κ = 2-2.2, triangularity δ = 0.4, internal inductance li = 0.6, Ejima coefficient CE = 0.35. Flux consumption efficiency results, performance improvements associated with first boronization and comparisons with neoclassical resistivity are described.",

author = "Menard, \{J. E.\} and LeBlanc, \{B. P.\} and Sabbagh, \{S. A.\} and Bell, \{M. G.\} and Bell, \{R. E.\} and Fredrickson, \{E. D.\} and Gates, \{D. A.\} and Jardin, \{S. C.\} and Johnson, \{D. W.\} and Kaye, \{S. M.\} and Kugel, \{H. W.\} and R. Maingi and Maqueda, \{R. J.\} and D. Mueller and M. Ono and F. Paoletti and Paul, \{S. F.\} and Skinnera, \{C. H.\} and D. Stutman",

year = "2001",

month = sep,

doi = "10.1088/0029-5515/41/9/308",

language = "English (US)",

volume = "41",

pages = "1197--1206",

journal = "Nuclear Fusion",

issn = "0029-5515",

publisher = "IOP Publishing Ltd.",

number = "9",

}

Menard, JE , LeBlanc, BP, Sabbagh, SA, Bell, MG, Bell, RE, Fredrickson, ED, Gates, DA, Jardin, SC, Johnson, DW, Kaye, SM, Kugel, HW, Maingi, R, Maqueda, RJ, Mueller, D, Ono, M, Paoletti, F, Paul, SF, Skinnera, CH & Stutman, D 2001, 'Ohmic flux consumption during initial operation of the NSTX spherical torus', Nuclear Fusion, vol. 41, no. 9, pp. 1197-1206. https://doi.org/10.1088/0029-5515/41/9/308

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T1 - Ohmic flux consumption during initial operation of the NSTX spherical torus

AU - Menard, J. E.

AU - LeBlanc, B. P.

AU - Sabbagh, S. A.

AU - Bell, M. G.

AU - Bell, R. E.

AU - Fredrickson, E. D.

AU - Gates, D. A.

AU - Jardin, S. C.

AU - Johnson, D. W.

AU - Kaye, S. M.

AU - Kugel, H. W.

AU - Maingi, R.

AU - Maqueda, R. J.

AU - Mueller, D.

AU - Ono, M.

AU - Paoletti, F.

AU - Paul, S. F.

AU - Skinnera, C. H.

AU - Stutman, D.

PY - 2001/9

Y1 - 2001/9

N2 - Spherical tokamaks, because of their slender central columns, have very limited volt second capability relative to that of standard aspect ratio tokamaks of similar plasma cross-section. Recent experiments on NSTX have begun to quantify and optimize the ohmic current drive efficiency in an MA class ST device. Sustainable ramp rates in excess of 5 MA/s during the current rise phase have been achieved on NSTX, while faster ramps generate significant MHD activity. Discharges with Ip exceeding 1 MA have been achieved in NSTX with nominal parameters: aspect ratio A = 1.3-1.4, elongation κ = 2-2.2, triangularity δ = 0.4, internal inductance li = 0.6, Ejima coefficient CE = 0.35. Flux consumption efficiency results, performance improvements associated with first boronization and comparisons with neoclassical resistivity are described.

AB - Spherical tokamaks, because of their slender central columns, have very limited volt second capability relative to that of standard aspect ratio tokamaks of similar plasma cross-section. Recent experiments on NSTX have begun to quantify and optimize the ohmic current drive efficiency in an MA class ST device. Sustainable ramp rates in excess of 5 MA/s during the current rise phase have been achieved on NSTX, while faster ramps generate significant MHD activity. Discharges with Ip exceeding 1 MA have been achieved in NSTX with nominal parameters: aspect ratio A = 1.3-1.4, elongation κ = 2-2.2, triangularity δ = 0.4, internal inductance li = 0.6, Ejima coefficient CE = 0.35. Flux consumption efficiency results, performance improvements associated with first boronization and comparisons with neoclassical resistivity are described.

UR - https://www.scopus.com/pages/publications/0035470101

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SP - 1197

EP - 1206

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 9

ER -

Ohmic flux consumption during initial operation of the NSTX spherical torus

Abstract

All Science Journal Classification (ASJC) codes

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