Response of nanoclusters to heavy-ion irradiation in an Fe-12Cr ODS steel

Yu, Hao; Wang, S.L.; Zhang, Y F; Liu, Q.; Diao, S.Z.; Liu, P.P.; Oono, Naoko; Ukai, Shigeharu; Wan, Fang; Ohnuki, Somei; Qu, Zhan

doi:10.1016/j.fusengdes.2021.112759

Cited by 8 publications

(3 citation statements)

References 49 publications

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“…The growing interest in the development of the nuclear industry worldwide is, among many others, a driving force to explore and investigate new groups of radiation resistant materials. [1][2][3][4] Materials to be used as components of future fission and fusion reactors should be carefully selected due to harsh operational conditions. [5][6][7][8][9] Therefore, while investigating these new groups of materials for such applications, special attention should be given to the high radiation tolerance, high thermal and phase stabilities, and elevated mechanical properties.…”

Section: Introductionmentioning

confidence: 99%

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals

et al. 2023

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Section: Introductionmentioning

confidence: 99%

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals

et al. 2023

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“…ODS steel is strengthened by dispersing oxide particles, which strongly impede dislocation motion and thereby increase the onset stress of plastic deformation and creep resistance [ 2 , 3 ]. ODS ferritic/martensitic steels containing 9–12 mass% Cr have been developed as fuel cladding material because of their high creep strength at elevated temperatures and adequate resistance to neutron irradiation embrittlement [ 4 , 5 , 6 , 7 , 8 , 9 ]. The performance of ODS steel largely depends on the particle size and stability of the dispersed oxide nanoparticles [ 10 , 11 ].…”

Section: Introductionmentioning

confidence: 99%

Phase Equilibria of the Fe–Cr–Er Ternary System in the Range 973–1273 K

Nie

Yin

et al. 2023

Materials

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Phase relations of the Fe–Cr–Er system in the temperature range 973–1273 K were experimentally investigated using equilibrated alloys. The isothermal sections consisted of 9 single-phase regions, 16 two-phase regions, and 8 three-phase regions at 973 K and 1073 K. At 1273 K, the σ phase disappeared, and liquid appeared. All single phases had a solid solubility range that showed a downward trend with a decrease in temperature. The homogeneity range of the ErFe12−xCrx ternary compound was determined to be x = 1.8–4.5. The more accurate phase relations obtained in this work can better guide the preparation of Fe–Cr–Er alloys in actual production.

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“…The nano oxide particles are distributed mostly in the grains, but some of them have also been detected at the grain boundaries by TEM [ 8 ]. Many previous studies on ODS steels have focussed on the stability of nano oxide particles during irradiation by atom probe tomography (APT) and transmission electron microscope TEM [ 9 , 10 , 11 , 12 , 13 ]. A few investigations of segregation in ODS steels [ 14 , 15 , 16 ] have been carried out, particularly in regard to understanding the segregation at the grain boundaries when some nano oxide particles are distributed in the grain boundary [ 17 ].…”

Section: Introductionmentioning

confidence: 99%

Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation

et al. 2022

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Oxide-dispersion-strengthened (ODS) steels, which contain nano-scale Y-Ti-O particles, are being considered for high-temperature radiation environments of nuclear reactors. It is important to accurately characterize the structure of grain boundaries and understand the behavior of segregation at grain boundaries in ODS steels during irradiation. The effect of heavy ion irradiation at 700 °C on Nanostructured Ferritic Alloy 14YWT was investigated using Atom Probe Tomography. Enrichment of Cr occurs at the grain boundaries as well as at nano oxide particle surfaces in the unirradiated sample. The enrichment of Ti and Y at a grain boundary corresponds with Y-Ti-O nano oxide particles with larger size compared to those in the grain, and the Cr enrichment is particularly accentuated at these larger nano oxide particles. The segregation of W occurs at the grain boundaries that are without nano oxide particles. O is segregated at grain boundaries without oxide particles after irradiation. The segregation behavior of Cr, W, Ti, and Y at the grain boundary in the irradiated samples is similar to that in the unirradiated sample. The nano oxide particles embedded in the grain boundary are a primary reason for the increase in Cr segregation at the grain boundary.

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Response of nanoclusters to heavy-ion irradiation in an Fe-12Cr ODS steel

Cited by 8 publications

References 49 publications

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals

Phase Equilibria of the Fe–Cr–Er Ternary System in the Range 973–1273 K

Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation

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Response of nanoclusters to heavy-ion irradiation in an Fe-12Cr ODS steel

Cited by 8 publications

References 49 publications

Tuning heterogeneous ion-radiation damage by composition in NixFe1−x binary single crystals

Tuning heterogeneous ion-radiation damage by composition in NixFe1−x binary single crystals

Phase Equilibria of the Fe–Cr–Er Ternary System in the Range 973–1273 K

Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation

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Product

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About

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals

Tuning heterogeneous ion-radiation damage by composition in Ni_xFe_1−x binary single crystals