Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

Y. Corre; E. Joffrin; P. Monier-Garbet; Y. Andrew; G. Arnoux; M. Beurskens; S. Brezinsek; M. Brix; R. Buttery; I. Coffey; K. Crombe; E. De La Luna; R. Felton; C. Giroud; S. Hacquin; J. Hobirk; A. Huber; F. Imbeaux; S. Jachmich; M. Kempenaars; X. Litaudon; H. Leggate; T. Loarer; G. Maddison; E. Rachlew; J. Rapp; O. Sauter; A. Savchkov; G. Telesca; A. Widdowson; K. D. Zastrow; O. Zimmermann

doi:10.1088/0741-3335/50/11/115012

Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

Y. Corre, E. Joffrin, P. Monier-Garbet, Y. Andrew, G. Arnoux, M. Beurskens, S. Brezinsek, M. Brix, R. Buttery, I. Coffey, K. Crombe, E. De La Luna, R. Felton, C. Giroud, S. Hacquin, J. Hobirk, A. Huber, F. Imbeaux, S. Jachmich, M. KempenaarsX. Litaudon, H. Leggate, T. Loarer, G. Maddison, E. Rachlew, J. Rapp, O. Sauter, A. Savchkov, G. Telesca, A. Widdowson, K. D. Zastrow, O. Zimmermann

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Abstract

The performance of the 'hybrid' H-mode regime (long pulse operation with high neutron fluency) has been extensively investigated in JET during the 2005-2007 experimental campaign up to normalized pressure β_N = 3, toroidal magnetic field B_t = 1.7 T, with type I ELMs plasma edge conditions. The optimized external current drive sources, self-generated non-inductive bootstrap current and plasma core stability properties provide a good prospect of achieving a high fusion gain at reduced plasma current for long durations in ITER. One of the remaining issues is the erosion of the divertor target plates associated with the type I ELM regime. A possible solution could be to operate with a plasma edge in the type III ELM regime (reduced transient and stationary heat loads) obtained with impurity seeding. An integrated hybrid type III ELM regime with a normalized pressure β_N = 2.6 (P _NBI ∼ 20-22 MW) and a thermal confinement factor of has been recently successfully developed on JET with nitrogen seeding. This scenario shows good plasma edge condition (compatible with the future ITER-like wall on JET) and moderate MHD activity. In this paper, we report on the experimental development of the scenario (with plasma current I_p = 1.7 MA and magnetic field B_t = 1.7 T) and the trade-off between heat load reduction at the target plates and global confinement due to nitrogen seeding and type III ELM working conditions.

Original language	English
Article number	115012
Journal	Plasma Physics and Controlled Fusion
Volume	50
Issue number	11
DOIs	https://doi.org/10.1088/0741-3335/50/11/115012
State	Published - Nov 1 2008
Externally published	Yes

Funding

Funders	Funder number
Engineering and Physical Sciences Research Council	EP/G003955/1

UN SDGs

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

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10.1088/0741-3335/50/11/115012

Cite this

Corre, Y., Joffrin, E., Monier-Garbet, P., Andrew, Y., Arnoux, G., Beurskens, M., Brezinsek, S., Brix, M., Buttery, R., Coffey, I., Crombe, K., De La Luna, E., Felton, R., Giroud, C., Hacquin, S., Hobirk, J., Huber, A., Imbeaux, F., Jachmich, S., ... Zimmermann, O. (2008). Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET. Plasma Physics and Controlled Fusion, 50(11), Article 115012. https://doi.org/10.1088/0741-3335/50/11/115012

@article{e145634703c04473923cb30b1fc301c3,

title = "Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET",

abstract = "The performance of the 'hybrid' H-mode regime (long pulse operation with high neutron fluency) has been extensively investigated in JET during the 2005-2007 experimental campaign up to normalized pressure βN = 3, toroidal magnetic field Bt = 1.7 T, with type I ELMs plasma edge conditions. The optimized external current drive sources, self-generated non-inductive bootstrap current and plasma core stability properties provide a good prospect of achieving a high fusion gain at reduced plasma current for long durations in ITER. One of the remaining issues is the erosion of the divertor target plates associated with the type I ELM regime. A possible solution could be to operate with a plasma edge in the type III ELM regime (reduced transient and stationary heat loads) obtained with impurity seeding. An integrated hybrid type III ELM regime with a normalized pressure βN = 2.6 (P NBI ∼ 20-22 MW) and a thermal confinement factor of has been recently successfully developed on JET with nitrogen seeding. This scenario shows good plasma edge condition (compatible with the future ITER-like wall on JET) and moderate MHD activity. In this paper, we report on the experimental development of the scenario (with plasma current Ip = 1.7 MA and magnetic field Bt = 1.7 T) and the trade-off between heat load reduction at the target plates and global confinement due to nitrogen seeding and type III ELM working conditions.",

author = "Y. Corre and E. Joffrin and P. Monier-Garbet and Y. Andrew and G. Arnoux and M. Beurskens and S. Brezinsek and M. Brix and R. Buttery and I. Coffey and K. Crombe and {De La Luna}, E. and R. Felton and C. Giroud and S. Hacquin and J. Hobirk and A. Huber and F. Imbeaux and S. Jachmich and M. Kempenaars and X. Litaudon and H. Leggate and T. Loarer and G. Maddison and E. Rachlew and J. Rapp and O. Sauter and A. Savchkov and G. Telesca and A. Widdowson and Zastrow, {K. D.} and O. Zimmermann",

year = "2008",

month = nov,

day = "1",

doi = "10.1088/0741-3335/50/11/115012",

language = "English",

volume = "50",

journal = "Plasma Physics and Controlled Fusion",

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Corre, Y, Joffrin, E, Monier-Garbet, P, Andrew, Y, Arnoux, G, Beurskens, M, Brezinsek, S, Brix, M, Buttery, R, Coffey, I, Crombe, K, De La Luna, E, Felton, R, Giroud, C, Hacquin, S, Hobirk, J, Huber, A, Imbeaux, F, Jachmich, S, Kempenaars, M, Litaudon, X, Leggate, H, Loarer, T, Maddison, G, Rachlew, E, Rapp, J, Sauter, O, Savchkov, A, Telesca, G, Widdowson, A, Zastrow, KD & Zimmermann, O 2008, 'Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET', Plasma Physics and Controlled Fusion, vol. 50, no. 11, 115012. https://doi.org/10.1088/0741-3335/50/11/115012

TY - JOUR

T1 - Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

AU - Corre, Y.

AU - Joffrin, E.

AU - Monier-Garbet, P.

AU - Andrew, Y.

AU - Arnoux, G.

AU - Beurskens, M.

AU - Brezinsek, S.

AU - Brix, M.

AU - Buttery, R.

AU - Coffey, I.

AU - Crombe, K.

AU - De La Luna, E.

AU - Felton, R.

AU - Giroud, C.

AU - Hacquin, S.

AU - Hobirk, J.

AU - Huber, A.

AU - Imbeaux, F.

AU - Jachmich, S.

AU - Kempenaars, M.

AU - Litaudon, X.

AU - Leggate, H.

AU - Loarer, T.

AU - Maddison, G.

AU - Rachlew, E.

AU - Rapp, J.

AU - Sauter, O.

AU - Savchkov, A.

AU - Telesca, G.

AU - Widdowson, A.

AU - Zastrow, K. D.

AU - Zimmermann, O.

PY - 2008/11/1

Y1 - 2008/11/1

N2 - The performance of the 'hybrid' H-mode regime (long pulse operation with high neutron fluency) has been extensively investigated in JET during the 2005-2007 experimental campaign up to normalized pressure βN = 3, toroidal magnetic field Bt = 1.7 T, with type I ELMs plasma edge conditions. The optimized external current drive sources, self-generated non-inductive bootstrap current and plasma core stability properties provide a good prospect of achieving a high fusion gain at reduced plasma current for long durations in ITER. One of the remaining issues is the erosion of the divertor target plates associated with the type I ELM regime. A possible solution could be to operate with a plasma edge in the type III ELM regime (reduced transient and stationary heat loads) obtained with impurity seeding. An integrated hybrid type III ELM regime with a normalized pressure βN = 2.6 (P NBI ∼ 20-22 MW) and a thermal confinement factor of has been recently successfully developed on JET with nitrogen seeding. This scenario shows good plasma edge condition (compatible with the future ITER-like wall on JET) and moderate MHD activity. In this paper, we report on the experimental development of the scenario (with plasma current Ip = 1.7 MA and magnetic field Bt = 1.7 T) and the trade-off between heat load reduction at the target plates and global confinement due to nitrogen seeding and type III ELM working conditions.

AB - The performance of the 'hybrid' H-mode regime (long pulse operation with high neutron fluency) has been extensively investigated in JET during the 2005-2007 experimental campaign up to normalized pressure βN = 3, toroidal magnetic field Bt = 1.7 T, with type I ELMs plasma edge conditions. The optimized external current drive sources, self-generated non-inductive bootstrap current and plasma core stability properties provide a good prospect of achieving a high fusion gain at reduced plasma current for long durations in ITER. One of the remaining issues is the erosion of the divertor target plates associated with the type I ELM regime. A possible solution could be to operate with a plasma edge in the type III ELM regime (reduced transient and stationary heat loads) obtained with impurity seeding. An integrated hybrid type III ELM regime with a normalized pressure βN = 2.6 (P NBI ∼ 20-22 MW) and a thermal confinement factor of has been recently successfully developed on JET with nitrogen seeding. This scenario shows good plasma edge condition (compatible with the future ITER-like wall on JET) and moderate MHD activity. In this paper, we report on the experimental development of the scenario (with plasma current Ip = 1.7 MA and magnetic field Bt = 1.7 T) and the trade-off between heat load reduction at the target plates and global confinement due to nitrogen seeding and type III ELM working conditions.

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U2 - 10.1088/0741-3335/50/11/115012

DO - 10.1088/0741-3335/50/11/115012

M3 - Article

AN - SCOPUS:58149313587

SN - 0741-3335

VL - 50

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

IS - 11

M1 - 115012

ER -

Hybrid H-mode scenario with nitrogen seeding and type III ELMs in JET

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