Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

被引：30

作者：

Khirwadkar, S. S. ^{[1
]}

Singh, K. P. ^{[1
]}

Patil, Y. ^{[1
]}

Khan, M. S. ^{[1
]}

Buch, J. J. U. ^{[1
]}

Patel, Alpesh ^{[1
]}

Tripathi, Sudhir ^{[1
]}

Jaman, P. M. ^{[2
]}

Rangaraj, L. ^{[2
]}

Divakar, C. ^{[2
]}

机构：

[1] Inst Plasma Res, Gandhinagar, Gujarat, India

[2] CSIR, Div Mat Sci, Natl Aerosp Labs, Bangalore, Karnataka, India

来源：

FUSION ENGINEERING AND DESIGN | 2011年 / 86卷 / 9-11期

关键词：

Plasma facing component (PFC); Vacuum brazing; Plasma facing material (PFM); Micro-structural examination; Shear strength; Tensile strength; PLASMA-FACING COMPONENTS; TECHNOLOGIES;

D O I：

10.1016/j.fusengdes.2011.01.111

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 development of the fabrication technology of macro-brush configuration of tungsten (W) and carbon (graphite and CFC) plasma facing components (PFCs) for ITER like tokamak application is presented. The fabrication of qualified joint of PFC is a requirement for fusion tokamak. Vacuum brazing method has been employed for joining of W/CuCrZr and C/CuCrZr. Oxygen free high conductivity (OFHC) copper casting on W tiles was performed followed by machining, polishing and ultrasonic cleaning of the samples prior to vacuum brazing. The W/CuCrZr and graphite/CuCrZr based test mockups were vacuum brazed using silver free alloys. The mechanical shear and tensile strengths were evaluated for the W/CuCrZr and graphite/CuCrZr brazed joint samples. The micro-structural examination of the joints showed smooth interface. The details of fabrication and characterization procedure for macro-brush tungsten and carbon based PFC test mockups are presented. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：1736 / 1740

页数：5

共 12 条

[1] Armor and heat sink materials joining technologies development for ITER plasma facing components [J].