A full tungsten divertor for ITER: Physics issues and design status

被引：674

作者：

Pitts, R. A. ^{[1
]}

Carpentier, S. ^{[1
]}

Escourbiac, F. ^{[1
]}

Hirai, T. ^{[1
]}

Komarov, V. ^{[1
]}

Lisgo, S. ^{[1
]}

Kukushkin, A. S. ^{[1
]}

Loarte, A. ^{[1
]}

Merola, M. ^{[1
]}

Naik, A. Sashala ^{[1
]}

Mitteau, R. ^{[1
]}

Sugihara, M. ^{[1
]}

Bazylev, B. ^{[2
]}

Stangeby, P. C. ^{[3
]}

机构：

[1] ITER Org, F-13115 St Paul Les Durance, France

[2] Karlsruhe Inst Technol, IHM, D-76021 Karlsruhe, Germany

[3] Univ Toronto, Inst Aerosp Studies, N York, ON M3H 5T6, Canada

来源：

JOURNAL OF NUCLEAR MATERIALS | 2013年 / 438卷

关键词：

PLASMA; EROSION; BERYLLIUM; TARGETS; EVENTS; ARMOR;

D O I：

10.1016/j.jnucmat.2013.01.008

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Budget restrictions have forced the ITER Organization to reconsider the baseline divertor strategy, in which operations would begin with carbon (C) in the high heat flux regions, changing out to a full-tungsten (W) variant before the first nuclear campaigns. Substantial cost reductions can be achieved if one of these two divertors is eliminated. The new strategy implies not only that ITER would start-up on a full-W divertor, but that this component should survive until well into the nuclear phase. This paper considers the risks engendered by such an approach with regard to known W plasma-material interaction issues and briefly presents the current status of a possible full-W divertor design. (C) 2013 ITER Organization. Published by Elsevier B.V. All rights reserved.

引用

收藏

页码：S48 / S56

页数：9

相关论文

共 52 条

[1] Material erosion and erosion products in disruption simulation experiments at the MK-200 UG facility [J].

Arkhipov, NI ;

Bakhtin, VP ;

Kurkin, SM ;

Safronov, VM ;

Toporkov, DA ;

Vasenin, SG ;

Zhitlukhin, AM ;

Würz, H .

FUSION ENGINEERING AND DESIGN, 2000, 49-50 :151-156

[2] Be-W alloy formation in static and divertor-plasma simulator experiments [J].

Baldwin, M. J. ;

Doerner, R. P. ;

Nishijima, D. ;

Buchenauer, D. ;

Clift, W. M. ;

Causey, R. A. ;

Schmid, K. .

JOURNAL OF NUCLEAR MATERIALS, 2007, 363 :1179-1183

[3] ITER transient consequences for material damage: modelling versus experiments [J].

Bazylev, B. ;

Janeschitz, G. ;

Landman, I. ;

Pestchanyi, S. ;

Loarte, A. ;

Federici, G. ;

Merola, M. ;

Linke, J. ;

Zhitlukhin, A. ;

Podkovyrov, V. ;

Klimov, N. ;

Safronov, V. .

PHYSICA SCRIPTA, 2007, T128 :229-233

[4] Melt layer erosion of metallic armour targets during off-normal events in tokamaks [J].

Bazylev, B ;

Wuerz, H .

JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :69-73

[5] Experimental validation of 3D simulations of tungsten melt erosion under ITER-like transient loads [J].

Bazylev, B. ;

Janeschitz, G. ;

Landman, I. ;

Loarte, A. ;

Federici, G. ;

Merola, M. ;

Zhitlukhin, A. ;

Podkovyrov, V. ;

Klimov, N. ;

Linke, J. ;

Hirai, T. .

JOURNAL OF NUCLEAR MATERIALS, 2009, 390-91 :810-813

[6]

Bazylev B., FUSION SCI IN PRESS

[7] Erosion of macrobrush tungsten armor after multiple intense transient events in ITER [J].

Bazylev, BN ;

Janeschitz, G ;

Landman, IS ;

Pestchanyi, SE .

FUSION ENGINEERING AND DESIGN, 2005, 75-79 :407-411

[8] Analysis of structural changes and high-heat-flux tests on pre-damaged tungsten from tokamak melt experiments [J].

Coenen, J. W. ;

Philipps, V. ;

Brezinsek, S. ;

Pintsuk, G. ;

Tanabe, T. ;

Ueda, Y. ;

Samm, U. .

PHYSICA SCRIPTA, 2011, T145

[9] Analysis of tungsten melt-layer motion and splashing under tokamak conditions at TEXTOR [J].

Coenen, J. W. ;

Philipps, V. ;

Brezinsek, S. ;

Bazylev, B. ;

Kreter, A. ;

Hirai, T. ;

Laengner, M. ;

Tanabe, T. ;

Ueda, Y. ;

Samm, U. .

NUCLEAR FUSION, 2011, 51 (08)

[10] Tungsten melt layer motion and splashing on castellated tungsten surfaces at the tokamak TEXTOR [J].

Coenen, J. W. ;

Bazylev, B. ;

Brezinsek, S. ;

Philipps, V. ;

Hirai, T. ;

Kreter, A. ;

Linke, J. ;

Sergienko, G. ;

Pospieszczyk, A. ;

Tanabe, T. ;

Ueda, Y. ;

Samm, U. .

JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) :S78-S82

← 1 2 3 4 5 6 →