The oxidation behavior of 316L in simulated pressurized water reactor environments with cyclically changing concentrations of dissolved oxygen and hydrogen

Zhong, Xiangyu; Xia, Shuang; Xu, Jian; Shoji, Tetsuo

doi:10.1016/j.jnucmat.2018.09.049

Cited by 10 publications

(5 citation statements)

References 27 publications

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“…In the circuits, R s is the solution resistance; R f is the resistance of passive film; W is the Warburg impedance; and Q f represents the passive film capacitance. The presence of Warburg impedance in a passive system was commonly believed to be related to the vacancy migration under the electric field across the passive film [24], which has been widely reported in the investigations on austenitic stainless steels [24][25][26][27]. The presence of Warburg impedance indicated that the corrosion process of 316L was controlled not only by a charge transfer process but also by a diffusion control process.…”

Section: Eis Resultsmentioning

confidence: 90%

Comparison Study on the Semiconductive and Dissolution Behaviour of 316L and Alloy 625 in Hydrochloric Acid Solution

Wang

Zhang

et al. 2019

Acta Metall. Sin. (Engl. Lett.)

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The corrosion behaviour of 316L and Alloy 625 was investigated using cyclic polarization, electrochemical impedance spectroscopy, X-ray photoelectron spectroscopy, Auger electron spectroscopy and induced coupled plasma-optical emission spectrometer. The results indicated that Alloy 625 showed better corrosion resistance than 316L and the prolonging immersion time could enhance corrosion resistance of the two alloys. The passive film formed on the surface of 316L exhibited an electronic structure of p-p heterojunction, with Fe 3 O 4 and Cr 2 O 3 enriched in the outer and inner layers, respectively. However, Alloy 625 presented the electronic structure of n-p heterojunction dominated by the outer Fe 2 O 3 /NiFe 2 O 4 and inner Cr 2 O 3 . This resulted in the opposite semiconductive properties of the passive films formed on the two materials. In the acid solutions, Fe and Mo suffered from selective dissolution while Cr and Ni were relatively stable. The corrosion rates were mainly dominated by the dissolution of iron. Alloy 625 presented better corrosion resistance than 316L due to the obviously lower content of Fe and the higher content of Cr and Ni in the passive film. The continuously selective dissolution of iron resulted in the increase in Cr/Fe ratio in the passive film, which was responsible for the enhancement in corrosion resistance.

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Section: Eis Resultsmentioning

confidence: 90%

Comparison Study on the Semiconductive and Dissolution Behaviour of 316L and Alloy 625 in Hydrochloric Acid Solution

Wang

Zhang

et al. 2019

Acta Metall. Sin. (Engl. Lett.)

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“…To suppress the radiolytic oxidation of water, hydrogen overpressure by adding 25-50 cc/kg of dissolved hydrogen (DH) is introduced in the PWR. Oxygen can be introduced into the primary loop system by adding aerated water, oxygen, or H 2 O 2 during the plant shutdown process for the PWR [29,30]. This stabilizes the oxide, thereby reducing the release of radioactive materials into the coolant.…”

Section: Environment Of a Pwrmentioning

confidence: 99%

“…Only limited research [30,33,223] has been conducted on the effect of DH concentration on the corrosion of stainless steel in high-temperature water. In the study by Takumi et al, it was observed that increasing the DH slightly elevated the corrosion rate [33].…”

Section: Adjusting the Corrosion Potential Of Water And Molten Salt T...mentioning

confidence: 99%

Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys

Liu,

Lei,

Huang

2024

NUCL SCI TECH

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The synergistic damage effect of irradiation and corrosion of reactor structural materials has been a prominent research focus. This paper provides a comprehensive review of the synergistic effects on the third- and fourth-generation fission nuclear energy structural materials used in pressurized water reactors and molten salt reactors. The competitive mechanisms of multiple influencing factors, such as the irradiation dose, corrosion type, and environmental temperature, are summarized in this paper. Conceptual approaches are proposed to alleviate the synergistic damage caused by irradiation and corrosion, thereby promoting in-depth research in the future and solving this key challenge for the structural materials used in reactors.

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“…Hematite is less soluble and denser than magnetite under typical secondary circuit conditions, therefore a layer of hematite on the surface of magnetite can reduce the FAC rate in SG feed water train [9]. This agrees with the higher resistance under oxidizing conditions [10]. But hematite deposit on SG tubes is believed to promote the onset of intergranular attack (IGA) and SCC of SG tubes [11], which should be avoided for nuclear safety reason.…”

Section: Introductionmentioning

confidence: 95%

Mechanism and kinetics of hematite reduction under typical PWR secondary circuit condition

Chanéac

Berger

et al. 2020

Journal of Nuclear Materials

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Hydrazine is added into secondary circuit in order to eliminate oxygen and to impose a reducing potential. Another possible role of hydrazine is to reduce hematite potentially present and thus reduce risk of stress corrosion cracking of steam generator tubes. However, the latter effect of hydrazine is still not clear. In order to better understand the mechanism and the kinetics of hematite reduction by hydrazine under secondary circuit conditions (275°C, slightly alkaline, diluted hydrazine), an experimental study has been carried out. It was found that the reduction of hematite proceeds through the adsorption of hydrazine, surficial reduction and dissolution of hematite, and coprecipitation of well crystallized octahedral magnetite.

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The oxidation behavior of 316L in simulated pressurized water reactor environments with cyclically changing concentrations of dissolved oxygen and hydrogen

Cited by 10 publications

References 27 publications

Comparison Study on the Semiconductive and Dissolution Behaviour of 316L and Alloy 625 in Hydrochloric Acid Solution

Comparison Study on the Semiconductive and Dissolution Behaviour of 316L and Alloy 625 in Hydrochloric Acid Solution

Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys

Mechanism and kinetics of hematite reduction under typical PWR secondary circuit condition

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