Developments and high heat flux tests of divertor components for LHD

被引：13

作者：

Kubota, Y ^{[1
]}

Noda, N

Sagara, A

Sakamoto, R

Motojima, O

Fujita, I

Hino, T

Yamashina, T

Tokunaga, K

Yoshida, N

机构：

[1] Natl Inst Fus Sci, Toki 50952, Japan

[2] Hokkaido Univ, Fac Engn, Sapporo, Hokkaido 060, Japan

[3] Kyushu Univ, Appl Mech Res Inst, Kasuga, Fukuoka 816, Japan

来源：

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

关键词：

D O I：

10.1016/S0920-3796(98)00109-4

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：

To develop the divertor plates for the large helical device (LHD), several kinds of brazed modules (BM) and mechanical jointed modules (MJM) have been fabricated and their thermal properties evaluated using an electron beam facility. The MJM and BM will be used as divertor plates in low heat flux (approximate to 5 MW m(-2)) and high heat flux (approximate to 10 MW m(-2)) phases, respectively. Results of the high heat flux tests indicate that some types of BMs satisfy the requirements for the divertor plates. For MJM, the efforts to improve the thermal properties are now being made so as to satisfy the divertor plate requirements. To optimize the design and assembly procedures, divertor mockups of the MJM have been fabricated and installed inside a vacuum vessel mock-up of LHD. The developments of these divertor components and the results of the high heat flux tests are reviewed. (C) 1998 Elsevier Science S.A. All rights reserved.

引用

页码：247 / 252

页数：6

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