scholarly journals CORROSION OF REACTOR STRUCTURAL MATERIALS IN HIGH-TEMPERATURE WATER. PART 2. STATIC CORROSION BEHAVIOR AT 600 TO 680 F

1954 ◽  
Author(s):  
R Fowler ◽  
D Douglas ◽  
F Zyzes
Author(s):  
Morrall Daniel ◽  
Huang Yen-Jui ◽  
Yabuuchi Kiyohiro ◽  
Kimura Akihiko ◽  
Ishizaki Takahiro ◽  
...  

2011 ◽  
Vol 474-476 ◽  
pp. 1128-1131
Author(s):  
Wei Tang ◽  
He Xue ◽  
Dan Zhao

Environmentally assisted cracking (EAC) or stress corrosion cracking (SCC) of key structural materials in the environments of the light water reactor is one of the main problems for the management of the structural safety and service life of nuclear power plants. To understand the effect of oxide film thickness on SCC growth in structural materials in a high temperature water environment, the stress-strain field at the tip of a SCC in nickel base alloy constituted by base metal and oxide film was analyzed in this paper by finite element method using commercial software. The effects of oxide film thickness on the stress-strain field at the tip of the SCC was obtained, which provides a new insight into the research of the mechanism of SCC growth in structural materials in a high temperature water environment.


Scanning ◽  
2020 ◽  
Vol 2020 ◽  
pp. 1-8
Author(s):  
Huiling Zhou ◽  
Yipeng Chen ◽  
Yi Sui ◽  
Yunfei Lv ◽  
Zhiyuan Zhu ◽  
...  

The corrosion behavior of an ultralow iron nickel-based alloy Inconel 625 under high-temperature water has been evaluated. The results show that surface oxidation and pitting were the principal corrosion mechanisms of Inconel 625 during the initial immersion period. The surface layer of the oxide film is first Ni-enriched and then Fe-enriched as immersion time increases. The iron ions dissolved from the autoclave could lead to the formation of NiFe2O4 and have a great influence on the oxidation behavior of Inconel 625. The oxides nucleated by solid-state reactions with selective dissolution of Fe and Ni and then grew up through precipitation of cations from solution.


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