Effects of carbon doping on irradiation resistance of Fe38Mn40Ni11Al4Cr7 high entropy alloys

Shen, Shangkun; Chen, Feida; Tang, Xiaobin; Lin, Jiwei; Ge, Guojia; Liu, Jian

doi:10.1016/j.jnucmat.2020.152380

Cited by 28 publications

(5 citation statements)

References 53 publications

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“…Vacuum Levitation Melting Process: Vacuum levitation melting (VLM) is a novel induction melting furnace in which the raw metals are levitated in a crucible and alloyed by convective mixing by stirring while under a levitating force. VLM eliminates the contamination from the crucible, and the ingot retains a more uniform microstructure than when using the traditional arc melting technique [166][167][168][169].…”

Section: Shape/friction Stir Additive Processingmentioning

confidence: 99%

Feasibility Studies and Downselection of New Materials and Manufacturing Technologies for Nuclear Applications

Byun,

Collins,

Lin

et al. 2023

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Section: Shape/friction Stir Additive Processingmentioning

confidence: 99%

Feasibility Studies and Downselection of New Materials and Manufacturing Technologies for Nuclear Applications

Byun,

Collins,

Lin

et al. 2023

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“…Hardness of FeCoCrNiMn with 2 at.% of C alloy was higher than carbon free alloy [53]. Irradiation resistant was enhanced in Fe38Mn40Ni11Al4Cr7Cx alloy [54]. Refractory alloys also enhanced by the presence of carbon in small concentrations [55].…”

Section: Introductionmentioning

confidence: 95%

Microstructure and properties of FeCrMnNiCx compositionally complex bulk alloys

Muftah

Vishnyakov

2021

Vacuum

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“…In general, the materials manifest sharply declining performances in hardening and swelling under irradiation [12,[21][22][23][24][25][26][27][28][29]. Introducing several defects sinks can effectively enhance the radiation resistance of materials, such as oxide-dispersion-strengthened steels [30,31] and nanograined polycrystalline alloys [32].…”

Section: Introductionmentioning

confidence: 99%

“…Many studies have shown that these alloys participate in the damage cascade processes by which a considerable amount of information-the generation, distribution, and evolution of defects-is acquired in the mechanism of radiation resistance [49][50][51][52][53]. The defect clusters (vacancy clusters and interstitial clusters) become independent individuals for Ni-containing HEAs that play a vital role in inhibiting swelling [22,24,35,37,44,50]. The generation of dislocation during the process of the damage cascade is beneficial for reducing the radiation hardening of FeNiMnCr HEAs at room temperature and higher [41].…”

Section: Introductionmentioning

confidence: 99%

Defects Act in an “Introverted” Manner in FeNiCrCoCu High-Entropy Alloy under Primary Damage

Zhang,

Kan,

Liang

et al. 2024

Metals

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High-entropy alloys (HEAs) attract much attention as possible radiation-resistant materials due to their several unique properties. In this work, the generation and evolution of the radiation damage response of an FeNiCrCoCu HEA and bulk Ni in the early stages were explored using molecular dynamics (MD). The design, concerned with investigating the irradiation tolerance of the FeNiCrCoCu HEA, encompassed the following: (1) The FeNiCrCoCu HEA structure was obtained through a hybrid method that combined Monte Carlo (MC) and MD vs. the random distribution of atoms. (2) Displacement cascades caused by different primary knock-on atom (PKA) energy levels (500 to 5000 eV) of the FeNiCrCoCu HEA vs. bulk Ni were simulated. There was almost no element segregation in bulk FeNiCrCoCu obtained with the MD/MC method by analyzing the Warren–Cowley short-range order (SRO) parameters. In this case, the atom distribution was similar to the random structure that was selected as a substrate to conduct the damage cascade process. A mass of defects (interstitials and vacancies) was generated primarily by PKA departure. The number of adatoms grew, which slightly roughened the surface, and the defects were distributed deeper as the PKA energy increased for both pure Ni and the FeNiCrCoCu HEA. At the time of thermal spike, one fascinating phenomenon occurred where the number of Frenkel pairs for HEA was more than that for pure Ni. However, we obtained the opposite result, that fewer Frenkel pairs survived in the HEA than in pure Ni in the final state of the damage cascade. The number and size of defect clusters grew with increasing PKA energy levels for both materials. Defects were suppressed in the HEA; that is to say, defects were “cowards”, behaving in an introverted manner according to the anthropomorphic rhetorical method.

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Effects of carbon doping on irradiation resistance of Fe38Mn40Ni11Al4Cr7 high entropy alloys

Cited by 28 publications

References 53 publications

Feasibility Studies and Downselection of New Materials and Manufacturing Technologies for Nuclear Applications

Feasibility Studies and Downselection of New Materials and Manufacturing Technologies for Nuclear Applications

Microstructure and properties of FeCrMnNiCx compositionally complex bulk alloys

Defects Act in an “Introverted” Manner in FeNiCrCoCu High-Entropy Alloy under Primary Damage

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