Nodular corrosion inside the crevice of Alloy 690 in deaerated high-temperature chloride solution

2021 ◽  
pp. 109442
Author(s):  
Fangqiang Ning ◽  
Jibo Tan ◽  
Ziyu Zhang ◽  
Xiang Wang ◽  
Xinqiang Wu ◽  
...  
2021 ◽  
Vol 66 ◽  
pp. 163-176
Author(s):  
Fangqiang Ning ◽  
Jibo Tan ◽  
Ziyu Zhang ◽  
Xinqiang Wu ◽  
Xiang Wang ◽  
...  

Author(s):  
Guangfu Li ◽  
Liang Zhao ◽  
Xinghong Yang

Stress corrosion cracking (SCC) in high temperature water/vapor environments with chloride concentrated as impurity has been regarded as one of the main failure mechanisms for leakage events occurred in 304L and 316L stainless steel tubing of heavy-water collection system in CANDU reactors according to failure analysis. In this work, the SCC behaviors in high temperature environments with highly concentrated chloride of the 304L, 316L and Ni-based alloy 690 were characterized by performing tests with U-bend specimens in the liquid of boiling magnesium chloride solution, as well as in the vapors above the liquid, to provide basic data for selecting better materials. Effect of surface state was examined by testing the specimens with inner surfaces in as-received state and in grinding-polished state for comparison. Results showed that the stainless steels 304L and 316L were all susceptible to SCC both in the liquid and in the vapor above. No apparent difference in cracking susceptibility was found among the specimens with as-received original surface state and with grinding-polish surface state. All were mainly intergranular cracking. The 304L appeared more resistant to SCC than the 316L. Ni-based alloy 690 exhibited excellent resistance to the cracking, as no any cracks were found on all the specimens tested. However, general corrosion occurred on the specimens of 690 tested both in the liquid and in the vapor above.


2019 ◽  
Vol 467-468 ◽  
pp. 1104-1112
Author(s):  
Qiang Hou ◽  
Zhiyong Liu ◽  
Chengtao Li ◽  
Xiaogang Li ◽  
Jiamin Shao

2018 ◽  
Vol 34 (8) ◽  
pp. 1419-1427 ◽  
Author(s):  
Jiazhen Wang ◽  
Jianqiu Wang ◽  
Hongliang Ming ◽  
Zhiming Zhang ◽  
En-Hou Han

Author(s):  
Jongmin Kim ◽  
Woogon Kim ◽  
Minchul Kim

Abstract Thermally induced steam generator (SG) tube failures caused by hot gases from a damaged reactor core can result in a containment bypass event and may lead to release of fission products to the environment. A typical severe accident scenario is a station blackout (SBO) with loss of auxiliary feedwater. Alloy 690 which has increased the Cr content has been replaced for the SG tube due to its high corrosion resistance against stress corrosion cracking (SCC). However, there is lack of research on the high temperature creep rupture and life prediction model of Alloy 690. In this study, creep test was performed to estimate the high temperature creep rupture life of Alloy 690. Based on reported creep data and creep test results of Alloy 690 in this study, creep life extrapolation was carried out using Larson-Miller Parameter (LMP), Orr-Sherby-Dorn (OSD), Manson-Haferd Parameter (MHP), and Wilshire’s approach. And a hyperbolic sine (sinh) function to determine master curves in LMP, OSD and MHP methods was used for improving the creep life estimation of Alloy 690 material.


2018 ◽  
Vol 498 ◽  
pp. 289-300 ◽  
Author(s):  
A.-C.L. Kimmel ◽  
Thomas F. Malkowski ◽  
Steven Griffiths ◽  
Benjamin Hertweck ◽  
Thomas G. Steigerwald ◽  
...  

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