Conditions for the suppression of void formation during ion-bombardment

Plumton, D.L.; Attaya, H.; Wolfer, W.G.

doi:10.1016/0022-3115(84)90675-5

Cited by 16 publications

(3 citation statements)

References 6 publications

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“…However, as the injected population increased more rapidly, voids could not nucleate beyond ~900 nm. Although this absence can be ascribed to the defect imbalance and dpa rate effects mentioned previously, this absence is primarily a consequence of the former on void nucleation, where the incident ion serves as one-half of a Frenkel pair without an accompanying vacancy [44][45][46][47][48][49][50][51][52]. While this slight imbalance might seem to be very small, it has been demonstrated theoretically to have a very strong impact on suppression of void nucleation [52].…”

Section: Note Inmentioning

confidence: 99%

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Gigax

Chen

Kim

et al. 2016

Journal of Nuclear Materials

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Ferritic-martensitic alloys are required for advanced reactor components to survive 500-600 neutron-induced dpa. Ion-induced void swelling of ferritic-martensitic alloy T91 in the quenched and tempered condition has been studied using a defocused, non-rastered 3.5 MeV Fe-ion beam at 475°C to produce damage levels up to 1000 peak displacements per atom (dpa). The high peak damage level of 1000 dpa is required to reach 500-600 dpa level due to injected interstitial suppression of void nucleation in the peak dpa region, requiring data extraction closer to the surface at lower dpa levels. At a relatively low peak damage level of 250 dpa, voids began to develop, appearing first in the near-surface region. With increasing ion fluence, swelling was observed deeper in the specimen, but remained completely suppressed in the back half of the ion range, even at 1000 peak dpa. The local differences in dpa rate in the front half of the ion range induce an "internal temperature shift" that strongly influences the onset of swelling, with shorter transient regimes resulting from lower dpa rates, in agreement not only with observations in neutron irradiation studies but also in various ion irradiations. Swelling was accompanied by radiation-induced precipitation of Cu-rich and Si, Ni, Mn-rich phases were observed by atom probe tomography, indicating concurrent microchemical evolution was in progress. In comparison to other ferritic-martensitic alloys during ion irradiation, T91 exhibits good swelling resistance with a swelling incubation period of about 400 local dpa.

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Section: Note Inmentioning

confidence: 99%

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Gigax

Chen

Kim

et al. 2016

Journal of Nuclear Materials

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“…Indeed, ions used to irradiate a thick target come to rest at the end of time range in the material as interstitials atoms and could impact diffusion process or the creation of point defect clusters, for example. Prior studies have demonstrated the significant influence of the injected Fe atoms on ion-induced swelling [20][21][22][23][24][25][26][27]. Both experimental and theoretical works showed that injected ions suppress void swelling.…”

mentioning

confidence: 99%

Influence of injected interstitials on α′ precipitation in Fe–Cr alloys under self-ion irradiation

Tissot

Pareige

Meslin

et al. 2016

Materials Research Letters

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“…Cavity-denuded regions can be observed near regions of damage peak [18]. In order to compensate for the swelling suppression of extra interstitials, the implantation of insoluble helium before heavy-ion irradiation was frequently used to enhance cavity nucleation [11,[19][20][21]. However, the role of helium, particularly its concentration, is complicated in the evolution of swelling [22][23][24][25][26][27][28][29][30][31][32].…”

Section: Introductionmentioning

confidence: 99%

Cavity Swelling of 15-15Ti Steel at High Doses by Ion Irradiation

Liu,

Ma,

Fan

et al. 2024

Materials

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The titanium-stabilized austenitic stainless steel Fe-15Cr-15Ni, which shows enhanced resistance to irradiation swelling compared with more traditional 316Ti, has been selected as a core material for fast reactors. Data on the evolution of irradiation swelling in 15-15Ti steels at very high doses, which cannot be easily achieved by neutron irradiation, are still lacking. In this paper, the swelling behavior of the titanium-modified austenitic stainless steel 15-15Ti was investigated by pre-implantation of He at room temperature followed by Ni-ion irradiation at 580 °C to peak doses of 120, 240 and 400 dpa. Relatively small cavities were observed in the zone of helium implantation, while large cavities appeared in the region near the damage peak. A correction formula for the dpa curve was proposed and applied to samples with large swelling. It was found that the steady-state swelling rate of 15-15Ti remains at ~1%/dpa even at high doses. By comparing the swelling data of the helium-implanted and helium-free regions at same doses, 70 dpa and 122 dpa, the suppression of swelling by excessive helium can be deduced at such doses.

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Conditions for the suppression of void formation during ion-bombardment

Cited by 16 publications

References 6 publications

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Influence of injected interstitials on α′ precipitation in Fe–Cr alloys under self-ion irradiation

Cavity Swelling of 15-15Ti Steel at High Doses by Ion Irradiation

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