Prospects for steady-state scenarios on JET

X. Litaudon, J.P.S. Bizarro, C.D. Challis, F. Crisanti, P.C. De Vries, P. Lomas, F.G. Rimini, Tuomas Tala, R. Akers, Y. Andrew, G. Arnoux, J.F. Artaud, Yu F. Baranov, M. Beurskens, M. Brix, R. Cesario, E. De La Luna, W. Fundamenski, C. Giroud, N.C. Hawkes & 9 others A. Huber, E. Joffrin, R.A. Pitts, E. Rachlew, S.D.A. Reyes-Cortes, S.E. Sharapov, K.D. Zastrow, O. Zimmermann, and JET EFDA contributors

Research output: Contribution to journalArticleScientificpeer-review

18 Citations (Scopus)

Abstract

In the 2006 experimental campaign, progress has been made on JET to operate non-inductive scenarios at higher applied powers (31 MW) and density (nl ~ 4 × 1019 m−3), with ITER-relevant safety factor (q95 ~ 5) and plasma shaping, taking advantage of the new divertor capabilities. The extrapolation of the performance using transport modelling benchmarked on the experimental database indicates that the foreseen power upgrade (~45 MW) will allow the development of non-inductive scenarios where the bootstrap current is maximized together with the fusion yield and not, as in present-day experiments, at its expense. The tools for the long-term JET programme are the new ITER-like ICRH antenna (~15 MW), an upgrade of the NB power (35 MW/20 s or 17.5 MW/40 s), a new ITER-like first wall, a new pellet injector for edge localized mode control together with improved diagnostic and control capability. Operation with the new wall will set new constraints on non-inductive scenarios that are already addressed experimentally and in the modelling. The fusion performance and driven current that could be reached at high density and power have been estimated using either 0D or 1–1/2D validated transport models. In the high power case (45 MW), the calculations indicate the potential for the operational space of the non-inductive regime to be extended in terms of current (~2.5 MA) and density (nl > 5 × 1019 m−3), with high βN (βN > 3.0) and a fraction of the bootstrap current within 60–70% at high toroidal field (~3.5 T).
Original languageEnglish
Pages (from-to)1285-1292
JournalNuclear Fusion
Volume47
Issue number9
DOIs
Publication statusPublished - 2007
MoE publication typeA1 Journal article-refereed

Fingerprint

fusion
safety factors
injectors
pellets
extrapolation
antennas

Keywords

  • fusion energy
  • fusion reactors
  • plasma
  • plasma-wall interactions
  • ITER
  • JET
  • tokamak
  • current drive

Cite this

Litaudon, X., Bizarro, J. P. S., Challis, C. D., Crisanti, F., De Vries, P. C., Lomas, P., ... contributors, A. JET. EFDA. (2007). Prospects for steady-state scenarios on JET. Nuclear Fusion, 47(9), 1285-1292. https://doi.org/10.1088/0029-5515/47/9/027
Litaudon, X. ; Bizarro, J.P.S. ; Challis, C.D. ; Crisanti, F. ; De Vries, P.C. ; Lomas, P. ; Rimini, F.G. ; Tala, Tuomas ; Akers, R. ; Andrew, Y. ; Arnoux, G. ; Artaud, J.F. ; Baranov, Yu F. ; Beurskens, M. ; Brix, M. ; Cesario, R. ; De La Luna, E. ; Fundamenski, W. ; Giroud, C. ; Hawkes, N.C. ; Huber, A. ; Joffrin, E. ; Pitts, R.A. ; Rachlew, E. ; Reyes-Cortes, S.D.A. ; Sharapov, S.E. ; Zastrow, K.D. ; Zimmermann, O. ; contributors, and JET EFDA. / Prospects for steady-state scenarios on JET. In: Nuclear Fusion. 2007 ; Vol. 47, No. 9. pp. 1285-1292.
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abstract = "In the 2006 experimental campaign, progress has been made on JET to operate non-inductive scenarios at higher applied powers (31 MW) and density (nl ~ 4 × 1019 m−3), with ITER-relevant safety factor (q95 ~ 5) and plasma shaping, taking advantage of the new divertor capabilities. The extrapolation of the performance using transport modelling benchmarked on the experimental database indicates that the foreseen power upgrade (~45 MW) will allow the development of non-inductive scenarios where the bootstrap current is maximized together with the fusion yield and not, as in present-day experiments, at its expense. The tools for the long-term JET programme are the new ITER-like ICRH antenna (~15 MW), an upgrade of the NB power (35 MW/20 s or 17.5 MW/40 s), a new ITER-like first wall, a new pellet injector for edge localized mode control together with improved diagnostic and control capability. Operation with the new wall will set new constraints on non-inductive scenarios that are already addressed experimentally and in the modelling. The fusion performance and driven current that could be reached at high density and power have been estimated using either 0D or 1–1/2D validated transport models. In the high power case (45 MW), the calculations indicate the potential for the operational space of the non-inductive regime to be extended in terms of current (~2.5 MA) and density (nl > 5 × 1019 m−3), with high βN (βN > 3.0) and a fraction of the bootstrap current within 60–70{\%} at high toroidal field (~3.5 T).",
keywords = "fusion energy, fusion reactors, plasma, plasma-wall interactions, ITER, JET, tokamak, current drive",
author = "X. Litaudon and J.P.S. Bizarro and C.D. Challis and F. Crisanti and {De Vries}, P.C. and P. Lomas and F.G. Rimini and Tuomas Tala and R. Akers and Y. Andrew and G. Arnoux and J.F. Artaud and Baranov, {Yu F.} and M. Beurskens and M. Brix and R. Cesario and {De La Luna}, E. and W. Fundamenski and C. Giroud and N.C. Hawkes and A. Huber and E. Joffrin and R.A. Pitts and E. Rachlew and S.D.A. Reyes-Cortes and S.E. Sharapov and K.D. Zastrow and O. Zimmermann and contributors, {and JET EFDA}",
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Litaudon, X, Bizarro, JPS, Challis, CD, Crisanti, F, De Vries, PC, Lomas, P, Rimini, FG, Tala, T, Akers, R, Andrew, Y, Arnoux, G, Artaud, JF, Baranov, YF, Beurskens, M, Brix, M, Cesario, R, De La Luna, E, Fundamenski, W, Giroud, C, Hawkes, NC, Huber, A, Joffrin, E, Pitts, RA, Rachlew, E, Reyes-Cortes, SDA, Sharapov, SE, Zastrow, KD, Zimmermann, O & contributors, AJETEFDA 2007, 'Prospects for steady-state scenarios on JET', Nuclear Fusion, vol. 47, no. 9, pp. 1285-1292. https://doi.org/10.1088/0029-5515/47/9/027

Prospects for steady-state scenarios on JET. / Litaudon, X.; Bizarro, J.P.S.; Challis, C.D.; Crisanti, F.; De Vries, P.C.; Lomas, P.; Rimini, F.G.; Tala, Tuomas; Akers, R.; Andrew, Y.; Arnoux, G.; Artaud, J.F.; Baranov, Yu F.; Beurskens, M.; Brix, M.; Cesario, R.; De La Luna, E.; Fundamenski, W.; Giroud, C.; Hawkes, N.C.; Huber, A.; Joffrin, E.; Pitts, R.A.; Rachlew, E.; Reyes-Cortes, S.D.A.; Sharapov, S.E.; Zastrow, K.D.; Zimmermann, O.; contributors, and JET EFDA.

In: Nuclear Fusion, Vol. 47, No. 9, 2007, p. 1285-1292.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Prospects for steady-state scenarios on JET

AU - Litaudon, X.

AU - Bizarro, J.P.S.

AU - Challis, C.D.

AU - Crisanti, F.

AU - De Vries, P.C.

AU - Lomas, P.

AU - Rimini, F.G.

AU - Tala, Tuomas

AU - Akers, R.

AU - Andrew, Y.

AU - Arnoux, G.

AU - Artaud, J.F.

AU - Baranov, Yu F.

AU - Beurskens, M.

AU - Brix, M.

AU - Cesario, R.

AU - De La Luna, E.

AU - Fundamenski, W.

AU - Giroud, C.

AU - Hawkes, N.C.

AU - Huber, A.

AU - Joffrin, E.

AU - Pitts, R.A.

AU - Rachlew, E.

AU - Reyes-Cortes, S.D.A.

AU - Sharapov, S.E.

AU - Zastrow, K.D.

AU - Zimmermann, O.

AU - contributors, and JET EFDA

PY - 2007

Y1 - 2007

N2 - In the 2006 experimental campaign, progress has been made on JET to operate non-inductive scenarios at higher applied powers (31 MW) and density (nl ~ 4 × 1019 m−3), with ITER-relevant safety factor (q95 ~ 5) and plasma shaping, taking advantage of the new divertor capabilities. The extrapolation of the performance using transport modelling benchmarked on the experimental database indicates that the foreseen power upgrade (~45 MW) will allow the development of non-inductive scenarios where the bootstrap current is maximized together with the fusion yield and not, as in present-day experiments, at its expense. The tools for the long-term JET programme are the new ITER-like ICRH antenna (~15 MW), an upgrade of the NB power (35 MW/20 s or 17.5 MW/40 s), a new ITER-like first wall, a new pellet injector for edge localized mode control together with improved diagnostic and control capability. Operation with the new wall will set new constraints on non-inductive scenarios that are already addressed experimentally and in the modelling. The fusion performance and driven current that could be reached at high density and power have been estimated using either 0D or 1–1/2D validated transport models. In the high power case (45 MW), the calculations indicate the potential for the operational space of the non-inductive regime to be extended in terms of current (~2.5 MA) and density (nl > 5 × 1019 m−3), with high βN (βN > 3.0) and a fraction of the bootstrap current within 60–70% at high toroidal field (~3.5 T).

AB - In the 2006 experimental campaign, progress has been made on JET to operate non-inductive scenarios at higher applied powers (31 MW) and density (nl ~ 4 × 1019 m−3), with ITER-relevant safety factor (q95 ~ 5) and plasma shaping, taking advantage of the new divertor capabilities. The extrapolation of the performance using transport modelling benchmarked on the experimental database indicates that the foreseen power upgrade (~45 MW) will allow the development of non-inductive scenarios where the bootstrap current is maximized together with the fusion yield and not, as in present-day experiments, at its expense. The tools for the long-term JET programme are the new ITER-like ICRH antenna (~15 MW), an upgrade of the NB power (35 MW/20 s or 17.5 MW/40 s), a new ITER-like first wall, a new pellet injector for edge localized mode control together with improved diagnostic and control capability. Operation with the new wall will set new constraints on non-inductive scenarios that are already addressed experimentally and in the modelling. The fusion performance and driven current that could be reached at high density and power have been estimated using either 0D or 1–1/2D validated transport models. In the high power case (45 MW), the calculations indicate the potential for the operational space of the non-inductive regime to be extended in terms of current (~2.5 MA) and density (nl > 5 × 1019 m−3), with high βN (βN > 3.0) and a fraction of the bootstrap current within 60–70% at high toroidal field (~3.5 T).

KW - fusion energy

KW - fusion reactors

KW - plasma

KW - plasma-wall interactions

KW - ITER

KW - JET

KW - tokamak

KW - current drive

U2 - 10.1088/0029-5515/47/9/027

DO - 10.1088/0029-5515/47/9/027

M3 - Article

VL - 47

SP - 1285

EP - 1292

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 9

ER -

Litaudon X, Bizarro JPS, Challis CD, Crisanti F, De Vries PC, Lomas P et al. Prospects for steady-state scenarios on JET. Nuclear Fusion. 2007;47(9):1285-1292. https://doi.org/10.1088/0029-5515/47/9/027