Progress in the production of the W7-X divertor target modules

被引：3

作者：

Boscary, J. ^{[1
]}

Ehrke, G. ^{[2
]}

Greuner, H. ^{[1
]}

Junghanns, P. ^{[1
]}

Li, C. ^{[1
]}

Mendelevitch, B. ^{[1
]}

Springer, J. ^{[1
]}

Stadler, R. ^{[1
]}

机构：

[1] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany

[2] Max Planck Inst Plasma Phys, Wendelsteinstr 1, D-17498 Greifswald, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2019年 / 146卷

关键词：

Stellarator; Wendelstein; 7-X; Plasma facing component; Divertor; WENDELSTEIN; ELEMENTS; DESIGN;

D O I：

10.1016/j.fusengdes.2019.03.080

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 realization of the 19.6 m(2) highly heat loaded target area of the actively water-cooled divertor of Wendelstein 7-X (W7-X) requires the installation of 100 target modules distributed in ten discrete similar divertor units. A target module is water-cooled from manifolds to distribute the water equally between the target elements with flanged connections to the water supply system. A target element is made of a CuCr1Zr copper alloy heat sink armored with CFC NB31 files and designed to remove a stationary heat flux up to 10 MW/m(2). The production of the first 30 target modules has been successfully completed in the workshop of IPP-Garching. The quality of the finished target modules was systematically assessed as follows: visual inspections, measurement of the 3-D CFC target area, dynamic pressure tests, integral He leak testing under pressure at different conditions (20 degrees C, 4 MPa and 160 degrees C, 2.5 MPa) in a vacuum oven, high heat flux testing. Only 2 finished target modules did not pass the integral He leak testing and were successfully repaired.

引用

页码：1975 / 1978

页数：4

共 14 条

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