Divertor heat load in ITER-like advanced tokamak scenarios on JET

G. Arnoux; P. Andrew; M. Beurskens; S. Brezinsek; C. D. Challis; P. De Vries; W. Fundamenski; E. Gauthier; C. Giroud; A. Huber; S. Jachmich; X. Litaudon; R. A. Pitts; F. Rimini

doi:10.1016/j.jnucmat.2009.01.094

Divertor heat load in ITER-like advanced tokamak scenarios on JET

G. Arnoux, P. Andrew, M. Beurskens, S. Brezinsek, C. D. Challis, P. De Vries, W. Fundamenski, E. Gauthier, C. Giroud, A. Huber, S. Jachmich, X. Litaudon, R. A. Pitts, F. Rimini

Laboratory for Plasma Physics

Research output: Contribution to journal › Article › peer-review

Abstract

Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (n_{e, av} < 5 × 10¹⁹ m^{- 3} at JET) to maximise the non inductive current drive, leading to high target temperature (20 < T_e < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (n_{e, av} ≃ 10 × 10¹⁹ m^{- 3}), show that for similar input power (≃ 20 MW) the outer target heat load is higher by a factor 4 in AT scenario, and is above the limit for the ITER-like wall (ILW). Operating long pulses in AT scenarios in the ILW could then be an issue and heat load reduction using impurity seeding is investigated.

Original language	English
Pages (from-to)	263-266
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	390-391
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2009.01.094
Publication status	Published - 15 Jun 2009

Access to Document

10.1016/j.jnucmat.2009.01.094

Cite this

@article{adea56173be5499cbfec90367d4d94b9,

title = "Divertor heat load in ITER-like advanced tokamak scenarios on JET",

abstract = "Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (ne, av < 5 × 1019 m- 3 at JET) to maximise the non inductive current drive, leading to high target temperature (20 < Te < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (ne, av ≃ 10 × 1019 m- 3), show that for similar input power (≃ 20 MW) the outer target heat load is higher by a factor 4 in AT scenario, and is above the limit for the ITER-like wall (ILW). Operating long pulses in AT scenarios in the ILW could then be an issue and heat load reduction using impurity seeding is investigated.",

author = "G. Arnoux and P. Andrew and M. Beurskens and S. Brezinsek and Challis, {C. D.} and Vries, {P. De} and W. Fundamenski and E. Gauthier and C. Giroud and A. Huber and S. Jachmich and X. Litaudon and Pitts, {R. A.} and F. Rimini",

year = "2009",

month = jun,

day = "15",

doi = "10.1016/j.jnucmat.2009.01.094",

language = "English",

volume = "390-391",

pages = "263--266",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

number = "1",

}

TY - JOUR

T1 - Divertor heat load in ITER-like advanced tokamak scenarios on JET

AU - Arnoux, G.

AU - Andrew, P.

AU - Beurskens, M.

AU - Brezinsek, S.

AU - Challis, C. D.

AU - Vries, P. De

AU - Fundamenski, W.

AU - Gauthier, E.

AU - Giroud, C.

AU - Huber, A.

AU - Jachmich, S.

AU - Litaudon, X.

AU - Pitts, R. A.

AU - Rimini, F.

PY - 2009/6/15

Y1 - 2009/6/15

N2 - Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (ne, av < 5 × 1019 m- 3 at JET) to maximise the non inductive current drive, leading to high target temperature (20 < Te < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (ne, av ≃ 10 × 1019 m- 3), show that for similar input power (≃ 20 MW) the outer target heat load is higher by a factor 4 in AT scenario, and is above the limit for the ITER-like wall (ILW). Operating long pulses in AT scenarios in the ILW could then be an issue and heat load reduction using impurity seeding is investigated.

AB - Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (ne, av < 5 × 1019 m- 3 at JET) to maximise the non inductive current drive, leading to high target temperature (20 < Te < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (ne, av ≃ 10 × 1019 m- 3), show that for similar input power (≃ 20 MW) the outer target heat load is higher by a factor 4 in AT scenario, and is above the limit for the ITER-like wall (ILW). Operating long pulses in AT scenarios in the ILW could then be an issue and heat load reduction using impurity seeding is investigated.

UR - http://www.scopus.com/inward/record.url?scp=67349270884&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2009.01.094

DO - 10.1016/j.jnucmat.2009.01.094

M3 - Article

AN - SCOPUS:67349270884

SN - 0022-3115

VL - 390-391

SP - 263

EP - 266

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1

ER -

Divertor heat load in ITER-like advanced tokamak scenarios on JET

Abstract

Access to Document

Other files and links

Fingerprint

Cite this