High heat flux tests of mock-ups for ITER divertor application

被引：13

作者：

Giniatulin, R ^{[1
]}

Gervash, A ^{[1
]}

Komarov, VL ^{[1
]}

Makhankov, A ^{[1
]}

Mazul, I ^{[1
]}

Litunovsky, N ^{[1
]}

Yablokov, N ^{[1
]}

机构：

[1] Efremov Inst, St Petersburg 189631, Russia

来源：

FUSION ENGINEERING AND DESIGN | 1998年 / 39-40卷

关键词：

D O I：

10.1016/S0920-3796(98)00217-8

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：

One of the most difficult tasks in fusion reactor development is the designing, fabrication and high heat flux testing of actively cooled plasma facing components (PFCs). At present, for the ITER divertor project it is necessary to design and test components by using mock-ups which reflect the real design and fabrication technology. The cause of failure of the PFCs is likely to be through thermo-cycling of the surface with heat loads in the range 1-15 MW m(-2). Beryllium, tungsten and graphite are considered as the most suitable armour materials for the ITER divertor application. This work presents the results of the tests carried out with divertor mock-ups clad with beryllium and tungsten armour materials. The tests were carried out in an electron beam facility. The results of high heat flux screening tests and thermo-cycling tests in the heat load range 1-9 MW m(-2) are presented along with the results of metallographic analysis carried out after the tests. (C) 1998 Elsevier Science S.A. All rights reserved.

引用

页码：385 / 391

页数：7

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