Corrosion of engineering materials in a supercritical water cooled reactor: Characterization of oxide scales on Alloy 800H and stainless steel 316

Choudhry, Kashif I.; Mahboubi, S.; Botton, Gianluigi A.; Kish, Joseph R.; Svishchev, Igor M.

doi:10.1016/j.corsci.2015.07.035

Cited by 69 publications

(35 citation statements)

References 44 publications

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“…After the tests the samples were sectioned for surface analysis; the details and initial results have been presented elsewhere [26]. The samples used for the surface analyses were cut from the middle of the test section.…”

Section: Methodsmentioning

confidence: 99%

“…As Cr(VI) oxides are soluble in SCW, Cr release increases, whereas Fe(III) species can form either magnetite or hematite and therefore remain on the surface. The surface film on the sample exposed at 650 • C to 20 ppm oxygenated water was shown by XRD to consist of both magnetite and hematite [26]. Once a continuous layer of iron oxides has formed on the surface (Fig.…”

Section: Model Of Oxide Film Growthmentioning

confidence: 99%

“…The oxide on the sample exposed to oxygenated water appeared slightly thinner. X-ray diffraction measurements showed the outer oxide formed in the presence of 20 ppm oxygen was a mixture of magnetite and hematite [26].…”

Section: Time Dependence Of Dissolved Element Concentrationsmentioning

confidence: 99%

“…Cross-sectional (top) and surface morphologies (bottom) of the oxide layers formed on Alloy 800H in SCW at 650 • C, 25 MPa with (right) and without (left) added oxygen (20 ppm)[26]. White lines on the cross-sectional images show the locations of the line scans.…”

mentioning

confidence: 98%

“…EDS line scans of the oxide layers formed on Alloy 800H in SCW at 650 • C, 25 MPa with (bottom) and without (top) added oxygen (20 ppm)[26]. Line scan locations are noted inFig.…”

mentioning

confidence: 99%

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On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water

et al. 2016

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Section: Methodsmentioning

confidence: 99%

Section: Model Of Oxide Film Growthmentioning

confidence: 99%

Section: Time Dependence Of Dissolved Element Concentrationsmentioning

confidence: 99%

mentioning

confidence: 98%

“…EDS line scans of the oxide layers formed on Alloy 800H in SCW at 650 • C, 25 MPa with (bottom) and without (top) added oxygen (20 ppm)[26]. Line scan locations are noted inFig.…”

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confidence: 99%

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On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water

et al. 2016

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On the thermochemical hydrogen release rate and activity transport in a supercritical water‐cooled reactor

Choudhry

Kallikragas

Svishchev

2016

Materials & Corrosion

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Hydrogen evolution and activity release rates for stainless steel SS316 and nickel-based Alloy 800H at the supercritical water-cooled reactor (SCWR) conditions were estimated, together with amount of oxygen absorbed into the passivation oxide layers formed on both materials. Hydrogen evolution from an oxidized SS316 surface was found to be about six times larger than from Alloy 800H at constant temperature and pressure of 650 8C and 25 MPa. The largest 60 Co activity release rate due to corrosion was estimated to be for SS316 at 650 8C and at pH10. Because of a single loop design, the radioactive corrosion products of in-core surfaces of the SCWR are expected to be carried out-of-core with the supercritical coolant.

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Stress corrosion cracking behavior of 310S stainless steel in supercritical water at different temperature

Liu¹,

Tan²,

Jiang³

et al. 2018

Materials & Corrosion

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The stress corrosion cracking (SCC) behavior and tensile properties of 310S stainless steel were studied by slow strain rate tensile (SSRT) tests, which were carried out in oxygenated supercritical water at the temperature of 400, 550, and 620 °C, respectively. The distribution of chemical composition of oxide, tensile properties, fracture morphology of the materials were analyzed for evaluating the SCC susceptibility of 310S stainless steel, respectively. The results show that both the elongation and tensile strength decreased significantly with the increase of the temperature, implying that a higher temperature may lead to a higher SCC susceptibility. The remarkable changes of the morphology of the fracture surface and gauge surface of 310S stainless steel were observed at different temperatures, that is, from an entire ductile fracture at lower temperature to a brittle fracture at higher temperature. The temperature has significant effects on morphologies and thickness. Oxides with double layer were observed. TEM analysis revealed that the inner oxide layer is composed of Cr and O, and Ni‐enrichment can be observed to segregate at the metal‐oxide interface.

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Corrosion of engineering materials in a supercritical water cooled reactor: Characterization of oxide scales on Alloy 800H and stainless steel 316

Cited by 69 publications

References 44 publications

On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water

On-line monitoring of oxide formation and dissolution on alloy 800H in supercritical water

On the thermochemical hydrogen release rate and activity transport in a supercritical water‐cooled reactor

Stress corrosion cracking behavior of 310S stainless steel in supercritical water at different temperature

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