Effect of thermal aging on corrosion behavior of type 316H stainless steel in molten chloride salt

2021 ◽  
Vol 191 ◽  
pp. 109784
Author(s):  
Xiaoli Li ◽  
Litao Chang ◽  
Chengpeng Liu ◽  
Bin Leng ◽  
Xiangxi Ye ◽  
...  
Solar Energy ◽  
2021 ◽  
Vol 223 ◽  
pp. 1-10
Author(s):  
Sen Ren ◽  
Yanjun Chen ◽  
Xiang-Xi Ye ◽  
Li Jiang ◽  
Shuai Yan ◽  
...  

Metals ◽  
2019 ◽  
Vol 9 (5) ◽  
pp. 529 ◽  
Author(s):  
Federica Zanotto ◽  
Vincenzo Grassi ◽  
Andrea Balbo ◽  
Fabrizio Zucchi ◽  
Cecilia Monticelli

This paper reports the effects of thermal aging between 650 and 850 °C on the localized corrosion behavior of lean duplex stainless steel (LDSS 2404). Critical pitting temperature (CPT) and double loop electrochemical potentiokinetic reactivation (DL-EPR) tests were performed. The localization of pitting attack and intergranular corrosion (IGC) attack after DL-EPR was investigated by optical (OM) and scanning electron microscopy (SEM) and by focused ion beam (FIB) coupled to SEM. Thermal aging caused the precipitation of mainly chromium nitrides at grain boundaries. Aging at 650 °C or short aging times (5 min) at 750 °C caused nitride precipitation mainly at α/α grain boundaries as a result of fast diffusion of chromium in this phase. Aging at 850 °C or aging times from 10 to 60 min at 750 °C also allowed the precipitation at the α/γ interface. Nitrides at γ/γ grain boundaries were observed rarely and only after long aging times (60 min) at 850 °C. Electrochemical tests showed that in as-received samples, pitting attack only affected the α phase. Conversely, in aged samples, pitting and IGC attack were detected close to nitrides in correspondence of α/α and α/γ grain boundaries depending on aging temperatures and times.


2021 ◽  
pp. 109483
Author(s):  
Brendan D’Souza ◽  
Weiqian Zhuo ◽  
Qiufeng Yang ◽  
Amanda Leong ◽  
Jinsuo Zhang

2020 ◽  
Author(s):  
N Dianne Bull Ezell ◽  
Stephen Raiman ◽  
J Matthew Kurley ◽  
Joel McDuffee

Capsules containing NaCl-MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 non-consecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation-corrosion experiments in static molten salts, and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts.


2021 ◽  
Vol 182 ◽  
pp. 109285
Author(s):  
Brendan D’Souza ◽  
Amanda Leong ◽  
Qiufeng Yang ◽  
Jinsuo Zhang

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