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. Lomas; D.C. McDonald; Y.S. Na; S.D. Pinches; A. Staebler; Tuomas Tala; A. Tuccillo; K. D. Zastrow; JET-EFDA Contributors

doi:10.1088/0029-5515/45/7/010

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 journal › Article › Scientific › peer-review

108 Citations (Scopus)

Abstract

In 2003, the performance of the 'hybrid' regime was successfully validated in JET experiments up to β_N = 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.β_N/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 language	English
Pages (from-to)	626 - 634
Number of pages	9
Journal	Nuclear Fusion
Volume	45
Issue number	7
DOIs	https://doi.org/10.1088/0029-5515/45/7/010
Publication status	Published - 2005
MoE publication type	A1 Journal article-refereed

Keywords

JET
plasma
fusion energy
fusion reactors
ITER
Tokamak

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1088/0029-5515/45/7/010

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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., ... 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

@article{dd8023346dbc4890acae66ab8755c5bb,

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}",

year = "2005",

doi = "10.1088/0029-5515/45/7/010",

language = "English",

volume = "45",

pages = "626 -- 634",

journal = "Nuclear Fusion",

issn = "0029-5515",

publisher = "Institute of Physics IOP",

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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

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

SN - 0029-5515

VL - 45

SP - 626

EP - 634

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 7

ER -

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

Abstract

Keywords

UN SDGs

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