The effect of irradiation and post-irradiation annealing on the yield stress and microstructure of vanadium-carbon alloys

Takahashi, H.; Ohnuki, Somei; Takeyama, Taro; Kayano, Hideo

doi:10.1016/0022-3115(81)90567-5

Cited by 11 publications

(2 citation statements)

References 14 publications

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“…However, experimental observation of Cr RIS at the grain boundaries in ferritic/martensitic alloy does not show any clear trend, and in fact a much more complex segregation behavior as a function of irradiation dose. Both enrichment and depletion of Cr at the grain boundary has been observed [2,[6][7][8][9]. Further, Ohnuki et al [8] observed that the presence of other alloying elements also modify the RIS behavior of Cr.…”

Section: Introductionmentioning

confidence: 92%

Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation

Choudhury

Barnard

Tucker³

et al. 2011

Journal of Nuclear Materials

113

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Section: Introductionmentioning

confidence: 92%

Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation

Choudhury

Barnard

Tucker³

et al. 2011

Journal of Nuclear Materials

113

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“…A strong variation in RIS has been observed in austenitic Fe-Cr-Ni alloys with the change in irradiation temperature, flux, composition, and grain boundary type [22][23][24]. Although depletion of Cr is universally observed at grain boundaries in irradiated austenitic steels, the experimental observations on ferritic/martensitic (BCC) steels shows more complex behavior with either enrichment or depletion at the grain boundary depending on the detailed irradiation conditions [22,[24][25][26][27][28]. A similar complexity in RIS was reported in Fe-Cr-Mn based austenitic steels.…”

Section: Introductionmentioning

confidence: 99%

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

et al. 2016

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In recent years, high entropy alloys (HEAs) have attracted significant attention due to their excellent mechanical properties and good corrosion resistance, making them potential candidates for high temperature fission and fusion structural applications. However there is very little known about their radiation resistance, particularly at elevated temperatures relevant for energy applications. In the present study, a single phase (face centered cubic) concentrated solid solution alloy of composition 27%Fe-28%Ni-27%Mn-18%Cr was irradiated with 3 or 5.8 MeV Ni ions at temperatures ranging from room temperature to 700°C and midrange doses from 0.03 to 10 displacements per atom (dpa). Transmission electron microscopy (TEM), scanning transmission electron microscopy with energy dispersive x-ray spectrometry (STEM/EDS) and X-ray diffraction (XRD) were used to characterize the radiation defects and microstructural changes. Irradiation at higher temperatures showed evidence of relatively sluggish solute diffusion with limited solute depletion or enrichment at grain boundaries. The main microstructural feature at all temperatures was high-density small dislocation loops. Voids were not observed at any irradiation condition. Nano-indentation tests on specimens irradiated at room temperature showed a rapid increase in hardness ~35% and ~80% higher than the unirradiated value at 0.03 and 0.3 dpa midrange doses, respectively. The irradiation-induced hardening was less pronounced for 500°C irradiations (<20% increase after 3 dpa). Overall, the examined HEA material exhibits superior radiation resistance compared to conventional single phase Fe-Cr-Ni austenitic alloys such as stainless steels. The present study provides insight on the fundamental irradiation behavior of a single phase HEA material over a broad range of irradiation temperatures.

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Effect of interstitial impurities on positronium formed in voids of vanadium

et al. 1994

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The effect of irradiation and post-irradiation annealing on the yield stress and microstructure of vanadium-carbon alloys

Cited by 11 publications

References 14 publications

Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation

Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation

Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

Effect of interstitial impurities on positronium formed in voids of vanadium

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