Effect of Pressures on the Corrosion Behaviours of Materials at 625°C

Li, W.; Huang, Xiao; Li, J.; Woo, O.T.; Sanchez, Rainier Garcia; Bibby, C

doi:10.1007/s11837-016-2201-x

Cited by 9 publications

(10 citation statements)

References 11 publications

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“…Cr, Mn and Fe containing oxides with a thickness of 1 µm were observed along with some nodules as in the samples exposed to low atmospheric pressure in our case. Li and collaborators also found a similar Cr-, Mn-and Fe-rich oxide when exposing SS 310 to 29 MPa at 625 • C for 1000 h [6]. (2) Thick unprotective nodules develop because of either the presence of Nb-rich carbides in the surface and/or to localised Cr evaporation, and grow both in thickness and sideways at faster oxidation rate under high pressure, as observed by many other authors.…”

Section: Discussionsupporting

confidence: 58%

“…The elemental analysis of the external layer in our case is compatible with (Fe,Mn)3O4, whereas the inner layer is likely (Cr,Mn)2O3. This was also proposed by Yang and coworkers to form on 304H after 1000 h under flowing steam at 650 °C [19], and by Li et al when exposing SS310 to supercritical (29 MPa) steam at 625 °C [6]. The lower Cr content of the outer zone of the scale may be caused by Cr evaporation as proposed by other authors [8].…”

Section: Microstructure Of the Oxide Scales Developed Under Atmospheric Steamsupporting

confidence: 53%

“…It has been found that in the presence of enough Si, this very thin oxide forms and behaves as a diffusion barrier improving the oxidation resistance [30]. Indeed, Li and coworkers also observed this layer by TEM microscopy on SS310 exposed to atmospheric steam pressure at 625 °C [6]. Right on top of this layer, a thin Cr (23.7 in wt.%) and Mn (4.5 in wt.%) containing oxide measuring less than 1 µm is observed, and is in turn covered by an Ferich thicker oxide containing Mn (4.1 in wt.%) and very little Cr (3.5 in wt.%).…”

Section: Microstructure Of the Oxide Scales Developed Under Atmospheric Steammentioning

confidence: 96%

“…Indeed, the oxide scale was significantly thicker with an outer Fe oxide layer and an inner Fe-Cr spinel, whereas at 1 bar very thin pure chromia formed according to the author. Some other studies related to testing austenitic steels under ultra-supercritical steam can be found in the open literature at temperatures ranging from 600-800 • C, and in general, at higher pressure, higher oxidation rates are observed [6][7][8][9][10][11]. At lower temperatures (<700 • C), a thin protective Cr-rich oxide accompanied by the presence of deep and large oxide nodules was observed at relative short.…”

Section: Introductionmentioning

confidence: 97%

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Steam Oxidation of Aluminide-Coated and Uncoated TP347HFG Stainless Steel under Atmospheric and Ultra-Supercritical Steam Conditions at 700 °C

et al. 2020

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The efficiency of ultra-supercritical (USC) steam power plants is limited by the materials properties, in particular, the steam oxidation resistance of the currently used steels at temperatures higher than 600 °C. Under these conditions, steam oxidation results in the development of thick oxide scales which spall and can accumulate in tube bends leading to blockage, overheating and premature creep rupture, as well as erosion of downstream components such as steam valves and turbine blades. Most published work related to oxidation testing is carried out at atmospheric pressure, with significantly less testing of austenitic steels in supercritical steam, and rarely including protective coatings. Indeed, the effect of high-pressure steam in the oxidation process is not quite understood at present. This paper covers a comparison of the behaviour of TP347HFG stainless steel at 700 °C under atmospheric pressure and 25 MPa, with and without slurry-applied diffusion aluminide coatings. The results show a very protective behaviour of the aluminide coatings, which develop a very thin Al-rich protective oxide, and no significant difference between the two environments. In contrast, the uncoated steel exhibited a different behaviour. Indeed, under atmospheric pressure after 3000 h, very thin scales, rich in Cr and not surpassing 5 to 10 µm in thickness, covered the samples along with some much thicker Fe-rich oxide nodules (up to 150 µm). However, under 25 MPa, a thick multilayer scale with a non-homogeneous thickness oscillating between 10 to 120 µm was present. A microstructural investigation was undertaken on the oxidised uncoated and coated substrates. The results suggest that pressure increases the oxidation rate of the chromia former steels but that the oxidation mechanism remains the same. A mechanism is proposed, including early detachment of the outer growing scales under supercritical pressure.

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Section: Discussionsupporting

confidence: 58%

Section: Microstructure Of the Oxide Scales Developed Under Atmospheric Steamsupporting

confidence: 53%

Section: Microstructure Of the Oxide Scales Developed Under Atmospheric Steammentioning

confidence: 96%

Section: Introductionmentioning

confidence: 97%

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Steam Oxidation of Aluminide-Coated and Uncoated TP347HFG Stainless Steel under Atmospheric and Ultra-Supercritical Steam Conditions at 700 °C

et al. 2020

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“…Some of the candidate materials that can be used are stainless steels and high nickel-chromium alloys. The corrosion resistance of stainless steels to oxidation in SCW environment was recently studied [1][2][3][4][5][6][7][8]. These alloys exhibit the lowest weight gains among most of the candidate alloys that are under investigation [9,10].…”

Section: Introductionmentioning

confidence: 99%

Investigation of Oxidation Behavior of 304L and 310S Steels with Potential Application in Supercritical Water-cooled Nuclear Reactors

Galan¹,

Ducu²,

Fulger³

et al. 2020

Rev. Chim.

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Selecting proper candidate materials is one key issue for the development of the supercritical water-cooled nuclear reactor (SCWR). Designing or choosing the most fitting materials means better sustainability, economics and safety. As the supercritical water is a very aggressive corrosive media, corrosion becomes one challenging problem for the materials used in the SCWR. This paper involves the corrosion testing of two stainless steels (304L and 310S) and microstructure evaluation of samples after being exposed to supercritical water. The test parameters were set at the temperature of 550oC and the pressure of 25 MPa for up to 63 days. The samples were investigated using gravimetric corrosion test, optical microscopy, scanning electron microscopy coupled with energy dispersive X-ray spectroscopy. Results showed a lower corrosion performance, in terms of weight change and surface oxide formation, for 304L due to its low chromium content. 310S has excellent corrosion resistance because the chromium content is higher. The results obtained will be useful in future research of test protocol and development of alloys that could be used as reactor fuel cladding and other components in the SCWR.

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Effect of Water Density/Pressure on the Corrosion Behavior of 304 and 310 Stainless Steels

2017

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Effect of Pressures on the Corrosion Behaviours of Materials at 625°C

Cited by 9 publications

References 11 publications

Steam Oxidation of Aluminide-Coated and Uncoated TP347HFG Stainless Steel under Atmospheric and Ultra-Supercritical Steam Conditions at 700 °C

Steam Oxidation of Aluminide-Coated and Uncoated TP347HFG Stainless Steel under Atmospheric and Ultra-Supercritical Steam Conditions at 700 °C

Investigation of Oxidation Behavior of 304L and 310S Steels with Potential Application in Supercritical Water-cooled Nuclear Reactors

Effect of Water Density/Pressure on the Corrosion Behavior of 304 and 310 Stainless Steels

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