ITER tungsten divertor design development and qualification program

被引：189

作者：

Hirai, T. ^{[1
]}

Escourbiac, F. ^{[1
]}

Carpentier-Chouchana, S. ^{[1
]}

Fedosov, A. ^{[1
]}

Ferrand, L. ^{[1
]}

Jokinen, T. ^{[1
]}

Komarov, V. ^{[1
]}

Kukushkin, A. ^{[1
]}

Merola, M. ^{[1
]}

Mitteau, R. ^{[1
]}

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

Shu, W. ^{[1
]}

Sugihara, M. ^{[1
]}

Riccardi, B. ^{[2
]}

Suzuki, S. ^{[3
]}

Villari, R. ^{[4
]}

机构：

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

[2] C Josep Pla, F4E, E-08019 Barcelona, Spain

[3] Fus Res & Dev Directorate JAEA, JAEA, Naka, Ibaraki 3110193, Japan

[4] Assoc EURATOM ENEA Fus, I-00044 Frascati, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2013年 / 88卷 / 9-10期

关键词：

ITER; Tungsten; Divertor; Tungsten divertor; High heat flux;

D O I：

10.1016/j.fusengdes.2013.05.010

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

In November 2011, the ITER Council has endorsed the recommendation that a period of up to 2 years be set to develop a full-tungsten divertor design and accelerate technology qualification in view of a possible decision to start operation with a divertor having a full-tungsten plasma-facing surface. To ensure a solid foundation for such a decision, a full tungsten divertor design, together with a demonstration of the necessary high performance tungsten monoblock technology should be completed within the required timescale. The status of both the design and technology R&D activity is summarized in this paper. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：1798 / 1801

页数：4

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