Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water

Ning, Fangqiang; Wang, Xiang; Yang, Ying; Tan, Jun; Zhang, Ziyu; Jia, Dan; Wu, Xiaohu; Han, En‐Hou

doi:10.1016/j.jmst.2020.07.026

Cited by 45 publications

(5 citation statements)

References 48 publications

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“…They reported that the external layer was an Fe-rich spinel sometimes containing nickel (Ni) (Ni is not present in FeCrAl alloys but may still be present in the test water because of minor dissolution from the stainless steel piping and autoclave body). The presence of Al in the transition region between the Cr-rich oxide and the base metal was also reported by Was et al [19] and Ning et al [15] at higher tested temperatures of 320 • C and 360 • C, respectively. After testing tubes of Fe-13Cr-5Al for 100 days under PWR conditions, Ning et al [15] reported Al enrichment in the Cr-rich oxide.…”

Section: Matrix Matrixsupporting

confidence: 78%

“…The presence of Al in the transition region between the Cr-rich oxide and the base metal was also reported by Was et al [19] and Ning et al [15] at higher tested temperatures of 320 • C and 360 • C, respectively. After testing tubes of Fe-13Cr-5Al for 100 days under PWR conditions, Ning et al [15] reported Al enrichment in the Cr-rich oxide. The findings by Ning et al [15] were also corroborated by Qu et al [12] after testing 7-13% Cr FeCrAl for 4 months at 360 • C.…”

Section: Matrix Matrixsupporting

confidence: 78%

“…The inner portion of the internal oxide layer rich in Cr also contains some aluminum. Figure 2b shows that underneath the continuous Cr-rich oxide layer, there is a non-continuous enrichment in Al, which seems to be in the non-oxidized matrix, which is sometimes called the transition layer [15]. Figure 3 shows the thickness and composition of the oxide developed on the surface of a C26M tube specimen after one year of immersion in BWR NWC conditions.…”

Section: Oxides Under Oxidizing Conditions (Bwr Nwc)mentioning

confidence: 99%

“…After testing tubes of Fe-13Cr-5Al for 100 days under PWR conditions, Ning et al [15] reported Al enrichment in the Cr-rich oxide. The findings by Ning et al [15] were also corroborated by Qu et al [12] after testing 7-13% Cr FeCrAl for 4 months at 360 • C.…”

Section: Matrix Matrixmentioning

confidence: 99%

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Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Qu,

Yin,

Larsen

et al. 2024

CMD

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The corrosion-resistant properties of IronChromium–Aluminum (FeCrAl) alloys have been known for nearly a century. Since the 1950s, they have been explored for application in the generation of nuclear power. In the last decade, the focus has been on the use of FeCrAl as cladding for uranium dioxide fuel in light water reactors (LWRs). The corrosion resistance of this alloy depends on the oxide that it can develop on the surface. In LWRs in the vicinity of 300 °C, the external surface oxide of the FeCrAl cladding could be rich in Fe under oxidizing conditions but rich in Cr under reducing conditions. If there is an accident and the cladding is exposed to superheated steam, the cladding will protect itself by developing an alpha aluminum film on the surface.

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Section: Matrix Matrixsupporting

confidence: 78%

Section: Matrix Matrixsupporting

confidence: 78%

Section: Oxides Under Oxidizing Conditions (Bwr Nwc)mentioning

confidence: 99%

Section: Matrix Matrixmentioning

confidence: 99%

See 2 more Smart Citations

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Qu,

Yin,

Larsen

et al. 2024

CMD

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“…Because there is a large amount of adsorbed oxygen and carbon on the outmost surface, the data were distorted at 0 s sputtering [ 5 ]. The sputtering time was 60 s, 840 s, and 1500 s. Table 2 shows the binding energy of targeted oxides or hydroxides [ 12 , 33 , 34 , 35 , 36 , 37 , 38 , 39 , 40 ]. The peak of O 2− dominated throughout the sputtering progress, indicating that the oxide films were mainly oxides.…”

Section: Resultsmentioning

confidence: 99%

Crevice Corrosion Behavior of Alloy 690 in High-Temperature Aerated Chloride Solution

et al. 2022

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Crevice corrosion behavior of Alloy 690 in high-temperature aerated chloride solution was studied using a self-designed crevice device. The SEM, EDS, XRD, and XPS analyses results indicated that the oxide films outside the crevice consisted of Ni-Cr oxides containing a small amount of hydroxides, and the oxide films on crevice mouth consisted of a (Ni,Fe)(Fe,Cr)2O4 spinel oxides outer layer and a Cr(OH)3 inner layer, and the oxide films inside the crevice consisted of a α-CrOOH outer layer and a Cr(OH)3 inner layer. When crevice corrosion occurred, the hydrolysis of Cr3+ led to the formation of Cr(OH)3 inside the crevice, and caused the pH value of crevice solution to decrease, and Cl− migrated from outside the crevice into inside the crevice due to electrical neutrality principle and accumulation. When the water chemistry inside the crevice reached the critical value of active dissolution of metal, the active dissolution of metal inside the crevice occurred. In addition, (Ni,Fe)(Fe,Cr)2O4 spinel oxides on the crevice mouth were formed by the deposition of metal ions migrated from inside the crevice. The mechanism of crevice corrosion and the formation mechanism of oxide films at different regions were also discussed.

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Introduction

Xu¹,

Guo²

2021

Corrosion Characteristics, Mechanisms and Control Methods of Candidate Alloys in Sub- And Supercritical Water

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Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water

Cited by 45 publications

References 48 publications

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Crevice Corrosion Behavior of Alloy 690 in High-Temperature Aerated Chloride Solution

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