Electrochemical behaviour of 316L stainless steel exposed to representative chemistry in pressurised water reactors under proton radiation

Wang, M.; Perrin, Stéphane; Corbel, C.; Féron, Damien

doi:10.1016/j.jelechem.2014.10.015

Cited by 9 publications

(2 citation statements)

References 24 publications

(24 reference statements)

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“…These species can undergo oxidation (O 2 , H 2 O 2 , HO 2 ) or reduction ( e − aq , H, and H 2 ). Literature [100,[107][108][109][110][111] provides a detailed review of the important reactions associated with these species and explains the charge conservation of H + and OH − .…”

Section: Effect Of Irradiation Radiolysis On Corrosionmentioning

confidence: 99%

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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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Section: Effect Of Irradiation Radiolysis On Corrosionmentioning

confidence: 99%

“…The water radiolysis product H 2 O 2 affects the electrochemical corrosion potential [108,110,111]. Figure 11 [112] shows the change in the corrosion potential of 304 and 316 stainless steels as a function of the H 2 O 2 concentration.…”

Section: Effect Of Irradiation Radiolysis On Corrosionmentioning

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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Influence of Water Radiolysis on the Passive Properties of 316L‐Stainless Steel

Bérerd,

Moncoffre,

Martinet

et al. 2024

ChemPhysChem

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This work aims to study the effect of radiolytic species induced by water radiolysis on the passive behavior of 316L stainless steel. For this purpose, the stainless steel/neutral and aerated 0.02 M Na2SO4, electrolyte solution interface was irradiated with proton beams. A wide range of energies between 2 and 16 MeV was selected, varying the maximum of the energy deposition between 0.5 and 122 µm in water from the interface. The irradiation experiments were performed at the CEMHTI cyclotron in Orléans and the 4 MV Van de Graaff accelerator at IP2I in Lyon (France). A dedicated irradiation device implemented with a 3‐electrode cell dedicated to perform electrochemical measurements allows to measure the surface reactivity of the stainless steel as a function of the irradiation conditions. Results show that whatever the beam energy, the corrosion potential remains unchanged. It indicates that the very short‐lived, highly reactive radiolytic species drive the corrosion potential and not only the recombination products such H2O2 or H2. The stainless steel remains in the passive state whatever the irradiation conditions. However, it is shown that, during irradiation, the passive film is less protective. This evolution is attributed to radiolysis of bound water molecules in the passive film.

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Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water

Hanbury¹,

Was²

2017

The Minerals, Metals &Amp; Materials Series

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Electrochemical behaviour of 316L stainless steel exposed to representative chemistry in pressurised water reactors under proton radiation

Cited by 9 publications

References 24 publications

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

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

Influence of Water Radiolysis on the Passive Properties of 316L‐Stainless Steel

Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water

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