The 'hybrid' scenario in JET: Towards its validation for ITER

E. Joffrin, A.C.C. Sips, J.F. Artaud, A. Bécoulet, L. Bertalot, R. Budny, P. Buratti, P. Belo, C.D. Challis, F. Crisanti, M. De Baar, P. de Vries, C. Gormezano, C. Giroud, O. Gruber, G.T.A. Huysmans, F. Imbeaux, A. Isayama, X. Litaudon, P.J. LomasD.C. McDonald, Y.S. Na, S.D. Pinches, A. Staebler, Tuomas Tala, A. Tuccillo, K. D. Zastrow, JET-EFDA Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    88 Citations (Scopus)

    Abstract

    In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to βN = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (ρ*) corresponding to identical ASDEX Upgrade discharges. Stationary conditions have been achieved with the fusion figure of merit (H89.βN/q295) reaching 0.42 at q95 = 3.9. The JET discharges show similar MHD, edge and current profile behaviour, when compared with the ASDEX Upgrade. In addition, the JET experiments have extended the hybrid scenario operation at higher toroidal field of 2.4 T and lower ρ* towards the projected ITER values. Using this database, transport and confinement properties are characterized with respect to the standard H-mode regime. Moreover, trace tritium has been injected to assess the diffusion and convective coefficients of the fusion fuel. The maximization of confinement and stability properties provides, to this scenario, a good probability of achieving a high fusion gain at reduced plasma current for durations of up to 2000 s in ITER.
    Original languageEnglish
    Pages (from-to)626 - 634
    Number of pages9
    JournalNuclear Fusion
    Volume45
    Issue number7
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    fusion
    Larmor radius
    plasma currents
    tritium
    figure of merit
    diffusion coefficient
    transport properties
    coefficients
    profiles

    Keywords

    • JET
    • plasma
    • fusion energy
    • fusion reactors
    • ITER
    • Tokamak

    Cite this

    Joffrin, E., Sips, A. C. C., Artaud, J. F., Bécoulet, A., Bertalot, L., Budny, R., ... JET-EFDA Contributors (2005). The 'hybrid' scenario in JET: Towards its validation for ITER. Nuclear Fusion, 45(7), 626 - 634. https://doi.org/10.1088/0029-5515/45/7/010
    Joffrin, E. ; Sips, A.C.C. ; Artaud, J.F. ; Bécoulet, A. ; Bertalot, L. ; Budny, R. ; Buratti, P. ; Belo, P. ; Challis, C.D. ; Crisanti, F. ; De Baar, M. ; de Vries, P. ; Gormezano, C. ; Giroud, C. ; Gruber, O. ; Huysmans, G.T.A. ; Imbeaux, F. ; Isayama, A. ; Litaudon, X. ; Lomas, P.J. ; McDonald, D.C. ; Na, Y.S. ; Pinches, S.D. ; Staebler, A. ; Tala, Tuomas ; Tuccillo, A. ; Zastrow, K. D. ; JET-EFDA Contributors. / The 'hybrid' scenario in JET : Towards its validation for ITER. In: Nuclear Fusion. 2005 ; Vol. 45, No. 7. pp. 626 - 634.
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    title = "The 'hybrid' scenario in JET: Towards its validation for ITER",
    abstract = "In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to βN = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (ρ*) corresponding to identical ASDEX Upgrade discharges. Stationary conditions have been achieved with the fusion figure of merit (H89.βN/q295) reaching 0.42 at q95 = 3.9. The JET discharges show similar MHD, edge and current profile behaviour, when compared with the ASDEX Upgrade. In addition, the JET experiments have extended the hybrid scenario operation at higher toroidal field of 2.4 T and lower ρ* towards the projected ITER values. Using this database, transport and confinement properties are characterized with respect to the standard H-mode regime. Moreover, trace tritium has been injected to assess the diffusion and convective coefficients of the fusion fuel. The maximization of confinement and stability properties provides, to this scenario, a good probability of achieving a high fusion gain at reduced plasma current for durations of up to 2000 s in ITER.",
    keywords = "JET, plasma, fusion energy, fusion reactors, ITER, Tokamak",
    author = "E. Joffrin and A.C.C. Sips and J.F. Artaud and A. B{\'e}coulet and L. Bertalot and R. Budny and P. Buratti and P. Belo and C.D. Challis and F. Crisanti and {De Baar}, M. and {de Vries}, P. and C. Gormezano and C. Giroud and O. Gruber and G.T.A. Huysmans and F. Imbeaux and A. Isayama and X. Litaudon and P.J. Lomas and D.C. McDonald and Y.S. Na and S.D. Pinches and A. Staebler and Tuomas Tala and A. Tuccillo and Zastrow, {K. D.} and {JET-EFDA Contributors}",
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    Joffrin, E, Sips, ACC, Artaud, JF, Bécoulet, A, Bertalot, L, Budny, R, Buratti, P, Belo, P, Challis, CD, Crisanti, F, De Baar, M, de Vries, P, Gormezano, C, Giroud, C, Gruber, O, Huysmans, GTA, Imbeaux, F, Isayama, A, Litaudon, X, Lomas, PJ, McDonald, DC, Na, YS, Pinches, SD, Staebler, A, Tala, T, Tuccillo, A, Zastrow, KD & JET-EFDA Contributors 2005, 'The 'hybrid' scenario in JET: Towards its validation for ITER', Nuclear Fusion, vol. 45, no. 7, pp. 626 - 634. https://doi.org/10.1088/0029-5515/45/7/010

    The 'hybrid' scenario in JET : Towards its validation for ITER. / Joffrin, E.; Sips, A.C.C.; Artaud, J.F.; Bécoulet, A.; Bertalot, L.; Budny, R.; Buratti, P.; Belo, P.; Challis, C.D.; Crisanti, F.; De Baar, M.; de Vries, P.; Gormezano, C.; Giroud, C.; Gruber, O.; Huysmans, G.T.A.; Imbeaux, F.; Isayama, A.; Litaudon, X.; Lomas, P.J.; McDonald, D.C.; Na, Y.S.; Pinches, S.D.; Staebler, A.; Tala, Tuomas; Tuccillo, A.; Zastrow, K. D.; JET-EFDA Contributors.

    In: Nuclear Fusion, Vol. 45, No. 7, 2005, p. 626 - 634.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - The 'hybrid' scenario in JET

    T2 - Towards its validation for ITER

    AU - Joffrin, E.

    AU - Sips, A.C.C.

    AU - Artaud, J.F.

    AU - Bécoulet, A.

    AU - Bertalot, L.

    AU - Budny, R.

    AU - Buratti, P.

    AU - Belo, P.

    AU - Challis, C.D.

    AU - Crisanti, F.

    AU - De Baar, M.

    AU - de Vries, P.

    AU - Gormezano, C.

    AU - Giroud, C.

    AU - Gruber, O.

    AU - Huysmans, G.T.A.

    AU - Imbeaux, F.

    AU - Isayama, A.

    AU - Litaudon, X.

    AU - Lomas, P.J.

    AU - McDonald, D.C.

    AU - Na, Y.S.

    AU - Pinches, S.D.

    AU - Staebler, A.

    AU - Tala, Tuomas

    AU - Tuccillo, A.

    AU - Zastrow, K. D.

    AU - JET-EFDA Contributors,

    PY - 2005

    Y1 - 2005

    N2 - In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to βN = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (ρ*) corresponding to identical ASDEX Upgrade discharges. Stationary conditions have been achieved with the fusion figure of merit (H89.βN/q295) reaching 0.42 at q95 = 3.9. The JET discharges show similar MHD, edge and current profile behaviour, when compared with the ASDEX Upgrade. In addition, the JET experiments have extended the hybrid scenario operation at higher toroidal field of 2.4 T and lower ρ* towards the projected ITER values. Using this database, transport and confinement properties are characterized with respect to the standard H-mode regime. Moreover, trace tritium has been injected to assess the diffusion and convective coefficients of the fusion fuel. The maximization of confinement and stability properties provides, to this scenario, a good probability of achieving a high fusion gain at reduced plasma current for durations of up to 2000 s in ITER.

    AB - In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to βN = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (ρ*) corresponding to identical ASDEX Upgrade discharges. Stationary conditions have been achieved with the fusion figure of merit (H89.βN/q295) reaching 0.42 at q95 = 3.9. The JET discharges show similar MHD, edge and current profile behaviour, when compared with the ASDEX Upgrade. In addition, the JET experiments have extended the hybrid scenario operation at higher toroidal field of 2.4 T and lower ρ* towards the projected ITER values. Using this database, transport and confinement properties are characterized with respect to the standard H-mode regime. Moreover, trace tritium has been injected to assess the diffusion and convective coefficients of the fusion fuel. The maximization of confinement and stability properties provides, to this scenario, a good probability of achieving a high fusion gain at reduced plasma current for durations of up to 2000 s in ITER.

    KW - JET

    KW - plasma

    KW - fusion energy

    KW - fusion reactors

    KW - ITER

    KW - Tokamak

    U2 - 10.1088/0029-5515/45/7/010

    DO - 10.1088/0029-5515/45/7/010

    M3 - Article

    VL - 45

    SP - 626

    EP - 634

    JO - Nuclear Fusion

    JF - Nuclear Fusion

    SN - 0029-5515

    IS - 7

    ER -

    Joffrin E, Sips ACC, Artaud JF, Bécoulet A, Bertalot L, Budny R et al. The 'hybrid' scenario in JET: Towards its validation for ITER. Nuclear Fusion. 2005;45(7):626 - 634. https://doi.org/10.1088/0029-5515/45/7/010