Static and in situ TEM investigation of phase relationships, phase dissolution, and interface motion in Ag–Au–Cu alloy nanoparticles

2004 ◽  
Vol 52 (10) ◽  
pp. 2923-2935 ◽  
Author(s):  
K. Chatterjee ◽  
J.M. Howe ◽  
W.C. Johnson ◽  
M. Murayama
Keyword(s):  
In Situ Tem ◽  
Alloy Nanoparticles ◽  
Interface Motion ◽  
Phase Dissolution ◽  
Cu Alloy ◽  
Phase Relationships

scholarly journals Thermal Stability Study of Classically Immiscible Rh-Ag Alloy Nanoparticles by in situ TEM

2016 ◽  
Vol 22 (S3) ◽  
pp. 820-821
Author(s):  
Cecile S. Bonifacio ◽  
Pranaw Kunal ◽  
Haiqin Wan ◽  
Simon M. Humphrey ◽  
Judith C. Yang
Keyword(s):  
Thermal Stability ◽  
Stability Study ◽  
In Situ Tem ◽  
Alloy Nanoparticles ◽  
Thermal Stability Study

In situ TEM study of Au–Cu alloy nanoparticle migration and coalescence

2009 ◽  
Vol 44 (2) ◽  
pp. 601-607 ◽  
Author(s):  
Abhay Raj S. Gautam ◽  
James M. Howe
Keyword(s):  
In Situ Tem ◽  
Cu Alloy

In situ TEM observation of the glass-to-liquid transition of metallic glass in Fe–Zr–B–Cu alloy

2010 ◽  
Vol 63 (10) ◽  
pp. 1020-1023 ◽  
Author(s):  
Takeshi Nagase ◽  
Akimasa Yokoyama ◽  
Yukichi Umakoshi
Keyword(s):  
Metallic Glass ◽  
In Situ Tem ◽  
Cu Alloy ◽  
Liquid Transition

In situ TEM studies of irradiation effects for materials improvement

1991 ◽  
Vol 49 ◽  
pp. 452-453
Author(s):  
Charles W. Allen
Keyword(s):  
Nuclear Reactor ◽  
Austenitic Stainless Steels ◽  
High Energy ◽  
Point Of View ◽  
In Situ Tem ◽  
Irradiation Effects ◽  
Tem Analysis ◽  
Radiation Induced ◽  
Analytical Tools

Irradiation effects studies employing TEMs as analytical tools have been conducted for almost as many years as materials people have done TEM, motivated largely by materials needs for nuclear reactor development. Such studies have focussed on the behavior both of nuclear fuels and of materials for other reactor components which are subjected to radiation-induced degradation. Especially in the 1950s and 60s, post-irradiation TEM analysis may have been coupled to in situ (in reactor or in pile) experiments (e.g., irradiation-induced creep experiments of austenitic stainless steels). Although necessary from a technological point of view, such experiments are difficult to instrument (measure strain dynamically, e.g.) and control (temperature, e.g.) and require months or even years to perform in a nuclear reactor or in a spallation neutron source. Consequently, methods were sought for simulation of neutroninduced radiation damage of materials, the simulations employing other forms of radiation; in the case of metals and alloys, high energy electrons and high energy ions.

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