Irradiation resistance of a nanostructured 316 austenitic stainless steel

Rajan, P.B. Revathy; Monnet, I.; Hug, Éric; Etienne, Auriane; Enikeev, Nariman A.; Keller, Clément; Sauvage, Xavier; Valiev, Ruslan Z.; Radiguet, B.

doi:10.1088/1757-899x/63/1/012121

Cited by 17 publications

(8 citation statements)

References 8 publications

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“…Theoretical studies on nanomaterials by Bai et al [41] indicate an increased defect accumulation in the matrix with decreased boundary density. Rajan et al [42] also suggested that there is a depletion of vacancies due to grain boundaries that act as defect sinks resulting in a decreased bubble density in nanostructured austenitic stainless steel under He ion irradiation. The shorter distance to the surface in a NP facilitates the annihilation of vacancies via the ingress of interstitials without the need for the vacancy to migrate all the way to the sink as suggested by the modelling work of [31].…”

Section: Resultsmentioning

confidence: 99%

Enhanced Radiation Tolerance of Tungsten Nanoparticles to He Ion Irradiation

et al. 2018

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Materials exposed to plasmas in magnetic confinement nuclear reactors will accumulate radiation-induced defects and energetically implanted gas atoms (from the plasma and transmutations), of which insoluble helium (He) is likely to be the most problematic. The large surface-area-to-volume ratio exhibited by nanoporous materials provides an unsaturable sink with the potential to continuously remove both point defects and He. This property enhances the possibilities for these materials to be tailored for high radiation-damage resistance. In order to explore the potential effect of this on the individual ligaments of nanoporous materials, we present results on the response of tungsten (W) nanoparticles (NPs) to 15 keV He ion irradiation. Tungsten foils and various sizes of NPs were ion irradiated concurrently and imaged in-situ via transmission electron microscopy at 750 °C. Helium bubbles were not observed in NPs with diameters less than 20 nm but did form in larger NPs and the foils. No dislocation loops or black spot damage were observed in any NPs up to 100 nm in diameter but were found to accumulate in the W foils. These results indicate that a nanoporous material, particularly one made up of ligaments with characteristic dimensions of 30 nm or less, is likely to exhibit significant resistance to He accumulation and structural damage and, therefore, be highly tolerant to radiation.

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Section: Resultsmentioning

confidence: 99%

Enhanced Radiation Tolerance of Tungsten Nanoparticles to He Ion Irradiation

et al. 2018

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“…In metallic materials, maximum nanoscale depth can reach up to 0.2 microns, which is beneficial for assessing the mechanical properties of thin films and coatings [ 20 , 21 , 22 ]. On the other hand, nIIT has been successfully utilized, with specific reference to SS 316L, to inspect the effects of surface modifications, such as those induced by irradiation [ 23 ], pulsed plasma [ 24 ], nitriding [ 25 ], sol-gel thin coating [ 26 ], and more. To the best of the authors’ knowledge, no studies, except for the one published by [ 27 ] on the fatigue behavior of PBF-LB SS 316L under different orientations (vertically, horizontally and at a 45° angle) using Vickers instrumented macro-indentation, have been conducted on the elastoplastic behavior of either SS 316L steel or its PBF-LB counterpart.…”

Section: Introductionmentioning

confidence: 99%

Nanoscale and Tensile-Like Properties by an Instrumented Indentation Test on PBF-LB SS 316L Steel

Maizza,

Hafeez,

Varone

et al. 2024

Materials

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The mechanical properties of a defect-free laser melting (PBF-LB) deposit of an AISI 316L steel alloy were assessed by means of an instrumented indentation test (IIT), at both the macro- and nano-scales. The inherent non-equilibrium microstructure of the alloy was chemically homogenous and consisted of equiaxed grains and large-elongated grains (under the optical microscope) with irregular outlines composed of a much finer internal cell structure (under the scanning electron microscope). Berkovich and Vickers indenters were used to assess the indentation properties across individual grains (nano) and over multiple grains (macro), respectively. The nano-indentation over the X-Y plane revealed nearly constant indentation modulus across an individual grain but variable on average within different grains whose value depended on the relative orientation of the individual grain. The macro-indentation test was conducted to analyze the tensile-like properties of the polycrystalline SS 316L alloy over the X-Y and Y-Z planes. The macro-indentation test provided a reliable estimate of the ultimate tensile strength (UTS-like) of the alloy. Other indentation properties gave inconsistent results, and a post factum analysis was, therefore, conducted, by means of a new approach, to account for the presence of residual stresses. The already existing indentation data were supplemented with new repeated indentation tests to conduct a detailed analysis of the relaxation ability of compressive and tensile residual stresses. The developed methodology allows the effect of residual stresses and the reliability of measured macro-indentation properties to be examined as a function of a small group of indentation parameters.

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“…sprin ger. com/ journ al/ 40195. irradiation [11,12]. Interfaces between oxide inclusions and the matrix were also shown to act as effective defect sinks in oxide-dispersion-strengthened (ODS) steels [13,14].…”

Section: Introductionmentioning

confidence: 99%

Helium Bubble Growth in He+ Ions Implanted 304L Stainless Steel Processed by Laser Powder Bed Fusion During Post-Irradiation Annealing at 600 °C

Liu

Min

Jiang

et al. 2022

Acta Metall. Sin. (Engl. Lett.)

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The abundancy of defect sinks in the microstructure of laser powder bed fusion (LPBF) processed austenitic stainless steels was found to be beneficial for helium resistance. In the current study, the influence of the novel microstructure in LPBF processed 304L on the helium bubble growth behaviour was investigated using transmission electron microscopy in samples implanted with He + ion and post-irradiation annealing treated at 600 °C for 1 h. Two variants of LPBF processed 304L samples were used, one in as-built condition and the other solution-annealed. The comparison between the two samples indicated that the helium bubble growth was inhibited and remained stable in the as-built sample but coarsened significantly in the solution-annealed sample. The sub-grain boundaries and oxide nano-inclusions acted as defect sinks to trap helium atoms and inhibited the growth of helium bubble in the as-built sample under the post-irradiation annealing conditions used.

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Irradiation resistance of a nanostructured 316 austenitic stainless steel

Cited by 17 publications

References 8 publications

Enhanced Radiation Tolerance of Tungsten Nanoparticles to He Ion Irradiation

Enhanced Radiation Tolerance of Tungsten Nanoparticles to He Ion Irradiation

Nanoscale and Tensile-Like Properties by an Instrumented Indentation Test on PBF-LB SS 316L Steel

Helium Bubble Growth in He+ Ions Implanted 304L Stainless Steel Processed by Laser Powder Bed Fusion During Post-Irradiation Annealing at 600 °C

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