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. HawkesA. 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.
    @article{fbf0601521b54b5a8fac30b4335290d4,
    title = "Prospects for steady-state scenarios on JET",
    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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    issn = "0029-5515",
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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