Corrosion issues in pressurized water reactor (PWR) systems

Calvar, M. Le; Curières, Ian De

doi:10.1533/9780857095343.5.473

Cited by 17 publications

(4 citation statements)

References 58 publications

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“…In PWRs, austenitic stainless steel and Ni-based alloys are the primary materials used for structural components, in addition to zirconium alloy fuel cladding and pressure vessel steel [1,[25][26][27]. Table 1 presents an overview of the main materials used in the primary circuits of PWRs.…”

Section: Structural Materials Of Pwrsmentioning

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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Section: Structural Materials Of Pwrsmentioning

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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“…2 The 7 Li is suitable for using as a core coolant in thorium – based molten salt reactors and a pH regulator in fission reactors, with a required abundance of 99.99%. 3,4 The lithium isotopes with natural abundance clearly cannot meet the requirements of nuclear industry, and therefore must be separated and enriched.…”

Section: Introductionmentioning

confidence: 99%

Electromigration separation of lithium isotopes with B12C4, B15C5 and B18C6 systems

Zhao,

Zhou,

Meng

et al. 2024

New J. Chem.

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“…The main materials in PWR primary system ( Figure 1 ) are composed of 25% zirconium alloys as fuel cladding, 65% Ni-based alloys as steam generator (SG) tubes, 5% stainless steels (SS) as SG, and some carbon steels (CS). At the same time, stainless steels are also the main materials of piping in PWR primary circuit [ 1 , 2 ].…”

Section: Introductionmentioning

confidence: 99%

Thermodynamic Analysis and Crystallographic Properties of MFe2O4, MCr2O4 and MAl2O4 (M = Fe, Ni, Zn) Formed on Structural Materials in Pressurized Water Reactor Primary Circuit under Zinc and Zinc-aluminum Water Chemistry

Jiao

Zhang

2022

Entropy

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Zinc injection technology (zinc water chemistry, ZWC) was widely applied in pressurized water reactor (PWR) primary circuits to reduce radiation buildup and improve corrosion resistance of structural materials. The simultaneous injection of zinc-aluminium (ZAWC) is a novel implement created to replace part of Zn2+ by Al3+. It was reported ZAWC can improve further corrosion resistance of carbon steels and stainless steels. However, ZAWC sometimes showed even negative effects on Nickel-alloys. In this study, mechanism of formation of oxide film on metals was investigated. The reactions of Fe2+ Ni2+ in oxide films replaced by Zn2+, or Fe3+ replaced by Al3+ in ZAWC were analysed. The thermodynamic data and solubility of mixed oxides (ZnFe2O4, ZnCr2O4, and ZnAl2O4), the products of replace reactions, were calculated. According to the Gibbs free energy difference between products and reactants, values of the formation reaction of ZnFe2O4, ZnCr2O4, and ZnAl2O4 are extremely negative. Solubility of ZnAl2O4 is the lowest among mixed oxide products, which implies the oxide film composites of ZnAl2O4 may show a lower corrosion rate. In addition, the preferential formation of NiAl2O4 on Ni-based-alloy, under ZAWC, was discussed based on crystallographic properties of spinel, which was considered as the cause of negative effects of ZAWC on corrosion resistance of Nickel-alloys. This research provides an analytical basis for the study of thermodynamic stability of oxide films under different chemical chemistry and a theoretical basis for improving corrosion resistance of different metals and optimizing the chemical conditions of PWR primary circuit.

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Corrosion issues in pressurized water reactor (PWR) systems

Cited by 17 publications

References 58 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

Electromigration separation of lithium isotopes with B12C4, B15C5 and B18C6 systems

Thermodynamic Analysis and Crystallographic Properties of MFe2O4, MCr2O4 and MAl2O4 (M = Fe, Ni, Zn) Formed on Structural Materials in Pressurized Water Reactor Primary Circuit under Zinc and Zinc-aluminum Water Chemistry

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