Diffusion bonding of a Cu-Cr-Zr alloy to stainless steel and tungsten using nickel as an interlayer

被引:58
作者
Batra, IS [1 ]
Kale, GB
Saha, TK
Ray, AK
Derose, J
Krishnan, J
机构
[1] Bhabha Atom Res Ctr, Div Mat Sci, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Div Laser & Plasma Technol, Bombay 400085, Maharashtra, India
[3] Bhabha Atom Res Ctr, Ctr Design & Mfg, Bombay 400085, Maharashtra, India
来源
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 2004年 / 369卷 / 1-2期
关键词
diffusion bonding; Cu-Cr-Zr alloy; tungsten; stainless steel; EPMA;
D O I
10.1016/j.msea.2003.10.296
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
In the present work, diffusion bonding of Cu-1 wt.% Cr-0.1 wt.% Zr alloy to tungsten as well as to stainless steel 316 (SS) has been attempted using nickel as an interlayer. This could be achieved in a single step and the bonds were found to be metallurgically sound with the strength exceeding that of the sintered tungsten used in this work. (C) 2003 Elsevier B.V. All rights reserved.
引用
收藏
页码:119 / 123
页数:5
相关论文
共 10 条
[1]   Selection, development and characterisation of plasma facing materials for ITER [J].
Barabash, V ;
Akiba, M ;
Mazul, I ;
Ulrickson, M ;
Vieider, G .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :718-723
[2]   Armor and heat sink materials joining technologies development for ITER plasma facing components [J].
Barabash, V ;
Akiba, M ;
Cardella, A ;
Mazul, I ;
Odegard, BC ;
Plöchl, L ;
Tivey, R ;
Vieider, G .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 :1248-1252
[3]   Microstructure and properties of a Cu-Cr-Zr alloy [J].
Batra, IS ;
Dey, GK ;
Kulkarni, UD ;
Banerjee, S .
JOURNAL OF NUCLEAR MATERIALS, 2001, 299 (02) :91-100
[4]   Tubular transition joint between zircaloy-2 and stainless steel [J].
Bhanumurthy, K ;
Krishnan, J ;
Kale, GB ;
Fotedar, RK ;
Biswas, AR ;
Arya, RN .
JOURNAL OF MATERIALS PROCESSING TECHNOLOGY, 1995, 54 (1-4) :322-325
[5]  
George E., 1988, MECH METALL, P35
[6]   Evaluation of hot isostatic pressing for joining of fusion reactor structural components [J].
Ivanov, AD ;
Sato, S ;
Le Marois, G .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) :35-42
[7]   A review of the US joining technologies for plasma facing components in the ITER fusion reactor [J].
Odegard, BC ;
Cadden, CH ;
Watson, RD ;
Slattery, KT .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :329-334
[8]  
PHILIBERT J, 1997, DEFECT DIFFUS FORUM, V143, P529
[9]   Development of tungsten armor and bonding to copper for plasma-interactive components [J].
Smid, I ;
Akiba, M ;
Vieider, G ;
Plochl, L .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :160-172
[10]   Development of high-Z plasma facing components for ITER [J].
Watson, RD ;
Slattery, KT ;
Odegard, BC ;
Cadden, CH ;
McKechnie, TN ;
O'Dell, S ;
Tuchinskiy, L ;
Loutfy, R ;
Dyadko, E ;
Sastri, S ;
Gundaa, N ;
Karandikar, P .
FUSION TECHNOLOGY, 1998, 34 (03) :443-453