Oxidation of austenitic and ferritic/martensitic alloys in supercritical water

Gómez-Briceño, D.; Blázquez, Francisco Cuadros; Sáez-Maderuelo, A.

doi:10.1016/j.supflu.2013.03.014

Cited by 64 publications

(26 citation statements)

References 17 publications

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“…While there are similarities in plant design between the SCWR and current commercial reactors, the elevated temperature and alternate coolant phase requires that candidate materials be evaluated under these more extreme conditions. Extensive studies have been performed that describe the formation of oxide layers on austenitic steels in supercritical water [4][5][6][7][8][9][10][11][12][13]. It has been observed that oxide films form on austenitic steels in the following manner; first a porous chromium rich spinel (FeCr 2 O 4 ) and Cr 2 O 3 form on the surface of the alloy, allowing the diffusion of iron from the surface of the alloy through the film.…”

Section: Introductionmentioning

confidence: 99%

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Rodriguez

Chidambaram

2015

Applied Surface Science

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Corrosion of stainless steel 316 and Nitronic 50 exposed to supercritical and ultrasupercritical water was studied as a function of temperature and exposure time. Post-exposure surface analysis was performed using Raman and X-ray photoelectron spectroscopies to determine the chemistry of the oxides formed as a result of the exposure. When exposed to supercritical water, Nitronic 50 and stainless steel 316 were observed to have similar weight gains; however, stainless steel 316 was found to gain less weight than Nitronic 50 in exposure tests performed in ultrasupercritical water. Stainless steel 316 developed surface films primarily composed of iron oxides, while the surface of Nitronic 50 contained a mixture of iron, chromium and manganese oxides. Based on these analyses, the differences in weight gain and oxidation characteristics of the two materials are attributed to the higher concentration of Cr and Mn in Nitronic 50 compared to stainless steel 316.

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Section: Introductionmentioning

confidence: 99%

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Rodriguez

Chidambaram

2015

Applied Surface Science

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“…Austenitic stainless steels, nickel-based alloys and zirconium alloys are already widely used in the design of nuclear power plants and are regarded as possible candidate materials for the water bearing components of the proposed SCWR [6][7][8][9]. Several research papers have been published on the corrosion behavior of various materials including stainless steel and Nibased alloys, under SCW conditions [10][11][12][13][14][15][16][17][18][19][20][21][22]. At high temperatures, these materials can release significant amounts of hydrogen gas during the formation of a corrosion layer via the oxidation of the surface, and this has an effect on the corrosion rate of the material [23][24][25][26][27][28][29][30].…”

Section: Introductionmentioning

confidence: 99%

Alloy 800H under supercritical water conditions: a flow reactor study of corrosion and hydrogen evolution

Choudhry

Svishchev

Orlovskaya

2015

Materials & Corrosion

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Hydrogen evolution and corrosion rates for an Alloy 800H flow‐through reactor operating under supercritical water conditions were determined. Experiments were performed in the temperature range of 650 to 750 °C both with deoxygenated feed water, with an O2 concentration of less than 10 μg L−1 (ppb), and with a high oxygen concentration of around 20 mg L−1 (ppm). Effective rate constants for hydrogen evolution during the corrosion of an Alloy 800H were calculated to be 2.52×10−11, 2.88×10−11 and 4.30×10−11 mol cm−2 s−1, for the reactor temperatures of 650, 700 and 750 °C, respectively.

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Section: Introductionmentioning

confidence: 99%

“…The proposed design of SCWR in GIF consists of direct cycle system at a pressure of 25 MPa with coolant entering at 280°C and leaving at 620°C, having an average temperature of 500°C. [8][9] Above critical pressure, coolant boiling eliminates, and as a result, water remains in single phase throughout the system. [10][11] Metallic materials encounter with very severe environment above the critical point of water (374°C, 22.1 MPa), and it may lead to severe corrosion and SCC.…”

Section: Introductionmentioning

confidence: 99%

Behavior and susceptibility to stress corrosion cracking of a nickel‐based alloy in superheated steam and supercritical water

Khan

Zhang

Zhu

et al. 2018

Materials & Corrosion

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Stress corrosion cracking (SCC) behavior of Alloy 617 was studied to evaluate its suitability for Generation IV supercritical water reactor concept. A series of slow strain rate tensile (SSRT) tests at a constant strain rate of 5 × 10−7 s−1 were carried out in superheated steam and supercritical water over a pressure range of 0.1–25 MPa at 650 °C. SSRT test in dry N2 gas was also performed to compare the results in non‐corrosive environment with corrosive medium environment. Intergranular cracks were observed for all specimens regardless of the test environment. Alloy 617 showed susceptibility to SCC at the tested experimental conditions. The dominance of intergranular SCC was observed on the gage surface and fracture surface by using scanning electron microscope analysis. The effect of varying environmental conditions on SCC susceptibility is further discussed.

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Oxidation of austenitic and ferritic/martensitic alloys in supercritical water

Cited by 64 publications

References 17 publications

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Oxidation of stainless steel 316 and Nitronic 50 in supercritical and ultrasupercritical water

Alloy 800H under supercritical water conditions: a flow reactor study of corrosion and hydrogen evolution

Behavior and susceptibility to stress corrosion cracking of a nickel‐based alloy in superheated steam and supercritical water

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