Key ITER plasma edge and plasma-material interaction issues

G. Federici; P. Andrew; P. Barabaschi; J. Brooks; R. Doerner; A. Geier; A. Herrmann; G. Janeschitz; K. Krieger; A. Kukushkin; A. Loarte; R. Neu; G. Saibene; M. Shimada; G. Strohmayer; M. Sugihara

doi:10.1016/S0022-3115(02)01327-2

Key ITER plasma edge and plasma-material interaction issues

G. Federici, P. Andrew, P. Barabaschi, J. Brooks, R. Doerner, A. Geier, A. Herrmann, G. Janeschitz, K. Krieger, A. Kukushkin, A. Loarte, R. Neu, G. Saibene, M. Shimada, G. Strohmayer, M. Sugihara

Publikation: Beitrag in Fachzeitschrift › Konferenzartikel › Begutachtung

361 Zitate (Scopus)

Abstract

Some of the remaining crucial plasma edge physics and plasma-material interaction issues of the ITER tokamak are discussed in this paper, using either modelling or projections of experimental results from existing tokamak operation or relevant laboratory simulations. The paper covers the following subject areas at issue in the design of the ITER device: (1) plasma thermal loads during Type I ELMs and disruptions, ensuing erosion effects and prospects for mitigating measures, (2) control of co-deposited tritium inventory when carbon is used even on small areas in the divertor near the strike points, (3) efficiency of edge and core fuelling for expected pedestal densities in ITER, and (4) erosion and impurity transport with a full tungsten divertor. Directions and priorities of future research are proposed to narrow remaining uncertainties in the above areas.

Originalsprache	Englisch
Seiten (von - bis)	11-22
Seitenumfang	12
Fachzeitschrift	Journal of Nuclear Materials
Jahrgang	313-316
Ausgabenummer	SUPPL.
DOIs	https://doi.org/10.1016/S0022-3115(02)01327-2
Publikationsstatus	Veröffentlicht - März 2003
Extern publiziert	Ja
Veranstaltung	Plasma - Surface Interactions in Controlled Fusion Devices - Gifu, Japan Dauer: 26 Mai 2002 → 31 Mai 2002

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10.1016/S0022-3115(02)01327-2

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Federici, G., Andrew, P., Barabaschi, P., Brooks, J., Doerner, R., Geier, A., Herrmann, A., Janeschitz, G., Krieger, K., Kukushkin, A., Loarte, A., Neu, R., Saibene, G., Shimada, M., Strohmayer, G., & Sugihara, M. (2003). Key ITER plasma edge and plasma-material interaction issues. Journal of Nuclear Materials, 313-316(SUPPL.), 11-22. https://doi.org/10.1016/S0022-3115(02)01327-2

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abstract = "Some of the remaining crucial plasma edge physics and plasma-material interaction issues of the ITER tokamak are discussed in this paper, using either modelling or projections of experimental results from existing tokamak operation or relevant laboratory simulations. The paper covers the following subject areas at issue in the design of the ITER device: (1) plasma thermal loads during Type I ELMs and disruptions, ensuing erosion effects and prospects for mitigating measures, (2) control of co-deposited tritium inventory when carbon is used even on small areas in the divertor near the strike points, (3) efficiency of edge and core fuelling for expected pedestal densities in ITER, and (4) erosion and impurity transport with a full tungsten divertor. Directions and priorities of future research are proposed to narrow remaining uncertainties in the above areas.",

keywords = "B2-EIRENE code, Boundary plasmas, Divertor, ITER, Plasma-edge physics, Plasma-wall interaction",

author = "G. Federici and P. Andrew and P. Barabaschi and J. Brooks and R. Doerner and A. Geier and A. Herrmann and G. Janeschitz and K. Krieger and A. Kukushkin and A. Loarte and R. Neu and G. Saibene and M. Shimada and G. Strohmayer and M. Sugihara",

year = "2003",

month = mar,

doi = "10.1016/S0022-3115(02)01327-2",

language = "English",

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pages = "11--22",

journal = "Journal of Nuclear Materials",

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note = "Plasma - Surface Interactions in Controlled Fusion Devices ; Conference date: 26-05-2002 Through 31-05-2002",

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Federici, G, Andrew, P, Barabaschi, P, Brooks, J, Doerner, R, Geier, A, Herrmann, A, Janeschitz, G, Krieger, K, Kukushkin, A, Loarte, A, Neu, R, Saibene, G, Shimada, M, Strohmayer, G & Sugihara, M 2003, 'Key ITER plasma edge and plasma-material interaction issues', Journal of Nuclear Materials, Jg. 313-316, Nr. SUPPL., S. 11-22. https://doi.org/10.1016/S0022-3115(02)01327-2

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T1 - Key ITER plasma edge and plasma-material interaction issues

AU - Federici, G.

AU - Andrew, P.

AU - Barabaschi, P.

AU - Brooks, J.

AU - Doerner, R.

AU - Geier, A.

AU - Herrmann, A.

AU - Janeschitz, G.

AU - Krieger, K.

AU - Kukushkin, A.

AU - Loarte, A.

AU - Neu, R.

AU - Saibene, G.

AU - Shimada, M.

AU - Strohmayer, G.

AU - Sugihara, M.

PY - 2003/3

Y1 - 2003/3

N2 - Some of the remaining crucial plasma edge physics and plasma-material interaction issues of the ITER tokamak are discussed in this paper, using either modelling or projections of experimental results from existing tokamak operation or relevant laboratory simulations. The paper covers the following subject areas at issue in the design of the ITER device: (1) plasma thermal loads during Type I ELMs and disruptions, ensuing erosion effects and prospects for mitigating measures, (2) control of co-deposited tritium inventory when carbon is used even on small areas in the divertor near the strike points, (3) efficiency of edge and core fuelling for expected pedestal densities in ITER, and (4) erosion and impurity transport with a full tungsten divertor. Directions and priorities of future research are proposed to narrow remaining uncertainties in the above areas.

AB - Some of the remaining crucial plasma edge physics and plasma-material interaction issues of the ITER tokamak are discussed in this paper, using either modelling or projections of experimental results from existing tokamak operation or relevant laboratory simulations. The paper covers the following subject areas at issue in the design of the ITER device: (1) plasma thermal loads during Type I ELMs and disruptions, ensuing erosion effects and prospects for mitigating measures, (2) control of co-deposited tritium inventory when carbon is used even on small areas in the divertor near the strike points, (3) efficiency of edge and core fuelling for expected pedestal densities in ITER, and (4) erosion and impurity transport with a full tungsten divertor. Directions and priorities of future research are proposed to narrow remaining uncertainties in the above areas.

KW - B2-EIRENE code

KW - Boundary plasmas

KW - Divertor

KW - ITER

KW - Plasma-edge physics

KW - Plasma-wall interaction

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U2 - 10.1016/S0022-3115(02)01327-2

DO - 10.1016/S0022-3115(02)01327-2

M3 - Conference article

AN - SCOPUS:0037346718

SN - 0022-3115

VL - 313-316

SP - 11

EP - 22

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL.

T2 - Plasma - Surface Interactions in Controlled Fusion Devices

Y2 - 26 May 2002 through 31 May 2002

ER -

Key ITER plasma edge and plasma-material interaction issues

Abstract

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