Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440

Марголин, Б. З.; Shvetsova, V. A.; Sorokin, A. A.; Minkin, A. J.; Pirogova, N. E.

doi:10.1016/j.jnucmat.2021.152911

Cited by 14 publications

(4 citation statements)

References 33 publications

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“…There were observed wedge and plate-shaped martensite inclusions adjoined grain boundaries (Figure 4a, c) and martensite lamels inside grains (Figure 4b, c). In accordance with the model of intergranular crack nucleation [13], the martensite inclusions act as strong barriers for dislocations and slip bands. The volume growth of martensite phase leads to increase in internal stresses acting on grain boundaries to a critical level, when the conditions for microcrack nucleationmay be satisfied.…”

Section: Resultssupporting

confidence: 63%

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Yarovchuk

Dikov

Tsay

2022

J. Phys.: Conf. Ser.

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The results of SEM studies of fracture surfaces for the 12Cr18Ni9 austenitic steel ruptured under a fixedtensile load in FeCl3 water solutionand in air are presented. The samples of austenized, sensitized at 650° and irradiated with neutrons (to 1020n/cm2) steel were examined. It was shown thatirradiation hardening and sensitizing annealing increased the susceptibility of steel to intergranular cracking in corrosive solution. Structural features of formation of the strain-induced α’-martensite and its reinforcing effect on fracture in various environments are discussed.

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Section: Resultssupporting

confidence: 63%

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Yarovchuk

Dikov

Tsay

2022

J. Phys.: Conf. Ser.

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“…In addition, the OCP of irradiated sample was always higher than that of unirradiated sample. Figure 10 showed the equivalent electrical circuits (EEC) model of the EIS for the 321 SS samples according to the previous studies in electrolytes [4] . When considering the low-frequency region as a semicircle, the EEC adopted the film resistance model, as shown in Figure 10a, while a straight line corresponded to the diffusion impedance model, as shown in Figure 10b.…”

Section: Electrochemical Test Resultsmentioning

confidence: 99%

“…321 stainless steel (SS) is a derivative of 304SS, which inhibits crack growth and CrC precipitation by adding Ti, thereby obtaining better grain boundary stress corrosion resistance [1] . Because of these advantages, 321SS is generally applied in the secondary circuits [2] and the internals of pressure vessel [3] in WWER (the PWR in Russian), such as WWER-440 from Novovoronezh NPP [4] . However, despite the presence of Ti, stress corrosion cracking (SCC) or even irradiation assisted stress corrosion cracking (IASCC) still occur in 321 SS with the increased service time [5] .…”

Section: Introductionmentioning

confidence: 99%

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

Gao,

Cao,

et al. 2023

J. Phys.: Conf. Ser.

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The impacts of low dose irradiation on the behavior of electrochemical corrosion and irradiation assisted stress corrosion cracking for 321 stainless steel were studied using Fe2+ ion irradiation to simulate neutron radiation damage in primary circuit environment of pressurized water reactor. Low dose irradiation can improve the pitting resistance and reduce the cracking tendency of the alloy in B-Li solution to a certain extent, which was related to the δ phase content on the near-surface of the sample: The higher δ phase content on the near-surface of the 2 dpa irradiated sample was observed by grazing incident X-ray diffraction. In addition, the pits was significantly increased near micro-cracks for the unirradiated sample, indicating that the existence of pits induced the initiation of cracks. The research results provided an important reference for the failure mechanism of irradiation assisted stress corrosion cracking of core components.

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“…Additionally, the measurement of the microhardness for the irradiated A1 material was carried out on the metal cut from the baffle-former-barrel assembly or, briefly, from the baffle of the decommissioned WWER-440 from Unit 3 of the Novovoronezh nuclear power plant. This reactor was in service for 45 years and was decommissioned in 2016 [58]. irr , some part of the radiation defects, such as point defects and dislocation loops, formed at neutron irradiation dissociates.…”

Section: Specimens For Neutron Irradiationmentioning

confidence: 99%

A Link between Neutron and Ion Irradiation Hardening for Stainless Austenitic and Ferritic-Martensitic Steels

Margolin,

Sorokin,

Belyaeva

2024

Metals

Self Cite

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Radiation hardening is studied for stainless austenitic and ferritic-martensitic chromium steels after ion and neutron irradiation at various temperatures. Austenitic and ferritic-martensitic steels irradiated up to 30 dpa in various nuclear reactors and ion accelerators are studied at various temperatures. A change in Vickers microhardness is used as the radiation hardening parameter. A methodology is developed that allows one to determine the ion irradiation parameters, which ensure the radiation hardening of ferritic-martensitic and austenitic steels, as close as possible to the radiation hardening of the same steels under neutron irradiation. A transferability function is introduced to connect the irradiation temperatures for ion and neutron irradiation that provides the same radiation hardening. On the basis of the obtained experimental data, after ion and neutron irradiation the transferability functions are determined for the investigated austenitic and ferritic-martensitic steels, which connect the temperatures for ion and neutron irradiation and provide the same radiation hardening at a given damage dose.

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Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440

Cited by 14 publications

References 33 publications

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Effect of low dose irradiation of heavy ion on electrochemical corrosion and IASCC behavior of austenitic steel

A Link between Neutron and Ion Irradiation Hardening for Stainless Austenitic and Ferritic-Martensitic Steels

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