Electrochemical characterization of oxide film formed at high temperature on Alloy 690

Abraham, Geogy J.; Bhambroo, Rajan; Kain, Vivekanand; Shekhar, Rajiv; Dey, G.K.; Raja, V.S.

doi:10.1016/j.nucengdes.2011.11.018

Cited by 26 publications

(8 citation statements)

References 17 publications

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“…One of the main issues to overcome in pressurized water reactors (PWR) is the induced radioactive dose where deposited activities are mainly caused by 58 Co and 60 Co which are respectively the neutron activated compounds of 58 Ni and 59 Co. Indeed in a primary coolant environment alloy 690 releases nickel ions [2][3][4][5][6][7]. This phenomenon occurs in parallel with a more prominent generalized corrosion process responsible for the formation of a protective oxide layer [1,3,5,[8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Laser surface melting of nickel-based alloy reduces nickel release in the primary cooling system of a nuclear power plant

Pacquentin

Gouton

Caron

et al. 2021

Optics & Laser Technology

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The surface of Ni-based alloy 690 was treated using a sub-microsecond pulsed laser in order to reduce the amount of nickel released when the surface is exposed to the primary cooling system of pressurized water nuclear reactors. A 2D array of laser treatment parameter sets was investigated. The results on sample surfaces was characterized using interferometric microscopy, Scanning Electron Microscopy (SEM), Glow Discharge Optical Emission Spectrometry (GDOES) and X-ray Photoelectron Spectrometry (XPS). The treatment leading to a continuous and defect-free chromine surface having the minimum nickel content over about the first two nanometers and no subsurface chromium depletion was selected for the nickel release test. This selection criterion proved to be very efficient as the total amount of nickel released in a standard qualification test using a simulated primary coolant was reduced, compared to a non-treated surface, by a factor of 7 during the heating phase and by a factor of 3.7 on average over the whole month-long test.

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Section: Introductionmentioning

confidence: 99%

Laser surface melting of nickel-based alloy reduces nickel release in the primary cooling system of a nuclear power plant

Pacquentin

Gouton

Caron

et al. 2021

Optics & Laser Technology

View full text Add to dashboard Cite

show abstract

“…Physical and chemical properties of water play a significant role in corrosion processes that occur in aqueous environments. In the case of high‐temperature corrosion of nuclear materials in pressurized water reactors (PWRs) usually simulated primary or secondary coolant water of a PWR are used by corrosion engineers to investigate the resistance of materials used in steam generator tubes, shells, and so forth to different types of corrosion, including general electrochemical corrosion and stress corrosion cracking . The main aim of researchers, in general, is to develop effective programs to select the most suitable metals/alloys and minimize their corrosion rate in operating conditions of the nuclear reactors.…”

Section: Introductionmentioning

confidence: 99%

Water chemistry, solution resistivity, and oxygen reduction reaction in simulated primary coolant of pressurized water reactors

Zhang

Arjmand

2019

Materials & Corrosion

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The effect of temperature (25°C-300°C) on the ohmic potential drop (ΔE Ω ) and resistivity (R sol ) of a simulated primary coolant of the pressurized water reactors was investigated using electrochemical impedance spectroscopy (EIS) and galvanostatic potentiometry. The variations in the conductivity and pH of the solution showed that by increasing the temperature the magnitude of the R sol and therefore ΔE Ω of the system first decreases rapidly (until~150°C) and then reaches a relatively stable plateau value. Increasing the pressure of the system decreased the magnitude of the R sol in the oxygenated coolant. Investigation of the oxygen reduction reaction (ORR) on platinum (Pt), 316L stainless steel (SS), Alloy 690, and carbon steel revealed the great effect of water chemistry, in particular pH on the rate of the ORR on these materials. OH − adsorption on Pt reduced the rate of the ORR on this metal at temperatures higher than~100°C. Finally, it was found that higher H 3 O + concentrations reduce the rate of the ORR on iron-and nickel-based alloys, while increasing the OH − concentration at temperatures higher thañ 150°C accelerates the rate of the ORR on these alloys. K E Y W O R D Shigh-temperature water, iR compensation, primary coolant, solution resistivity

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“…The effects of various water chemistry parameters such as dissolved oxygen (DO) [ 6 ], pH [ 7 , 8 ], temperature [ 8 – 10 ], Li/B coordination [ 11 ], and Zn injection [ 12 , 13 ] on the oxidation behavior of nickel-based alloys have been investigated extensively. Besides, dissolved hydrogen (DH) is also an important parameter because it can significantly affect the oxide formation and the corrosion behavior of nickel-based alloys [ 14 – 17 ].…”

Section: Introductionmentioning

confidence: 99%

Effects of Hydrogen Contents on Oxidation Behavior of Alloy 690TT and Associated Boron Accumulation within Oxides in High-Temperature Water

2018

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The aim of this work is to characterize the oxide layer structure of Alloy 690TT in high-temperature water with different dissolved hydrogen (DH) contents by using an X-ray photoelectron spectroscopy. Under the low DH contents (0.4494–0.8988 mg/kg), the oxide layers were composed of an outermost layer of Ni(OH)2 and Cr(OH)3 enriched in Ni, an intermediate layer of hydroxides and oxides enriched in Cr, and an inner Cr2O3 layer. Outermost NiO coexists with small amount of Cr2O3 layer, while in the inner oxide only Cr2O3 remains. The oxide layers at medium and high DH contents (3.1458– 8.9880 mg/kg) consisted of an outermost layer of Ni(OH)2 and Cr(OH)3 enriched in Cr, an intermediate layer of metallic Ni, hydroxides and oxides enriched in Cr, and an inner Cr2O3 layer. In addition, boron compounds containing B3+ ions were accumulated in the thick and porous NiO layer formed at low DH contents, whereas the accumulation of boron compounds did not occur in the thin and dense polyhedral oxide layer formed at medium and high DH contents.

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Electrochemical characterization of oxide film formed at high temperature on Alloy 690

Cited by 26 publications

References 17 publications

Laser surface melting of nickel-based alloy reduces nickel release in the primary cooling system of a nuclear power plant

Laser surface melting of nickel-based alloy reduces nickel release in the primary cooling system of a nuclear power plant

Water chemistry, solution resistivity, and oxygen reduction reaction in simulated primary coolant of pressurized water reactors

Effects of Hydrogen Contents on Oxidation Behavior of Alloy 690TT and Associated Boron Accumulation within Oxides in High-Temperature Water

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