Overview of the engineering design of ITER divertor

被引：9

作者：

Ibbott, C ^{[1
]}

Chiocchio, S ^{[1
]}

D'Agata, E ^{[1
]}

Federici, G ^{[1
]}

Heidl, H ^{[1
]}

Janeschitz, G ^{[1
]}

Martin, E ^{[1
]}

Tivey, R ^{[1
]}

机构：

[1] ITER, Joint Cent Team, D-85748 Garching, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2001年 / 56-57卷

关键词：

ITER; plasma-facing components; carbon-tritium deposition;

D O I：

10.1016/S0920-3796(01)00294-0

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：

The ITER divertor cassettes, which support plasma-facing components (PFCs), provide the flexibility to adapt to changing design requirements imposed by the evolving understanding of divertor physics. This paper gives an overview of how the divertor has been adjusted to meet the most recent changes in the ITER design also describing some cost saving design simplifications. Furthermore, the paper deals with an overview of the engineering R&D, shared amongst the Home Teams, that is underway in support of PFC development, In particular the paper summarises the 'hot' liner R&D. This R&D has produced interesting laboratory results and their relevance in mitigating carbon-tritium deposition in ITER is discussed. (C) 2001 Elsevier Science BN. All rights reserved.

引用

页码：243 / 248

页数：6

共 9 条

[1] Overview of the Japanese mock-up tests for ITER high heat flux components [J].