Corrosion resistance of structural materials in media for production of polyvinyl butyral for optical applications

1986 ◽  
Vol 22 (8) ◽  
pp. 392-393
Author(s):  
O. A. Tarakanovskaya ◽  
N. P. Zhil'tsov ◽  
L. A. Vericheva ◽  
I. N. Nikolaeva
Author(s):  
A.A. Suslov

Because of their high specific strength and satisfactory corrosion resistance, aluminum alloys belong to the group of fundamental structural materials in modern engineering. Their wide use has been made possible as a result of developing advanced methods of processing and producing permanent joints by welding or brazing. However, the application of brazing aluminum alloys is limited because of the problems in removing the strong and chemically resistant oxide film. These problems can be overcome by using metallic coatings which themselves do not oxidize during heating in vacuum and, when deposited, the oxide film is broken up and can be removed from the surface of the parent material. The most promising method is to use metallic coatings in the form of individual components of the brazing alloy which forms in contact melting of the deposited coatings with aluminum in heating for brazing. This brazing method is referred to as contact-reactive brazing and is used widely for brazing aluminum alloys. This article provides an overview of the contact-reactive brazing process.


1978 ◽  
Vol 14 (4) ◽  
pp. 336-338
Author(s):  
Ts. L. Drukh ◽  
N. M. Davydenko ◽  
�. B. Gitis ◽  
F. I. Strigunov ◽  
I. A. Lagno ◽  
...  

2002 ◽  
Vol 303 (1) ◽  
pp. 73-81 ◽  
Author(s):  
Todd O. Sullivan ◽  
Nathan A. Byman ◽  
Frédéric Landry ◽  
David G. Kolman ◽  
Eric M. Taleff

2019 ◽  
pp. 35 ◽  
Author(s):  
Yu.V. Ponkratov ◽  
V.S. Bochkov ◽  
K.K. Samarkhanov ◽  
I.S. Karambayeva ◽  
S.K. Askerbekov

The behavior of structural materials of nuclear and fusion reactors during operation largely determines their safe and economical work. Structural materials of nuclear and fusion reactors are operating under conditions of interaction with various chemical active elements (gases, vapor-gas mixtures, fission products, etc.) in a wide temperature range; they are subject to high requirements in terms of their thermal and corrosion resistance. This paper presents the new methodology of complex studies on structural materials corrosion resistance of nuclear and fusion reactors with different gases and vapor-gas mixtures by thermal-gravimetric analysis (TGA), differential-scanning calorimetry (DSC) and mass spectrometry (MS) methods simultaneously.


Alloy Digest ◽  
1987 ◽  
Vol 36 (1) ◽  

Abstract BRUSH WELLMAN S-65B is a grade of beryllium strengthened by a dispersion of beryllium oxide. It has moderate strength and fairly low ductility (a minimum of 3% elongation). Its uses include optical applications, nuclear reactors, instrumentation, X-ray windows, high-speed computer parts, audio components and aerospace structural applications. This datasheet provides information on composition, physical properties, elasticity, and tensile properties as well as fracture toughness. It also includes information on corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Be-3. Producer or source: Brush Wellman Inc..


Alloy Digest ◽  
1987 ◽  
Vol 36 (8) ◽  

Abstract BRUSH WELLMAN I-70A is an instrument and optical grade of beryllium strengthened by a dispersion of 0.7% beryllium oxide maximum. It has relatively low strength and fairly low ductility (a minimum of 2% elongation). Its uses include optical applications, instrumentation, and optical-instrumentation applications. This datasheet provides information on composition, physical properties, elasticity, and tensile properties as well as fracture toughness. It also includes information on corrosion resistance as well as forming, heat treating, joining, and surface treatment. Filing Code: Be-6. Producer or source: Brush Wellman Inc..


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