Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor

Laborne, Alexandra Renault; Gavoille, P.; Malaplate, J.; Pokor, C.; Tanguy, B.

doi:10.1016/j.jnucmat.2015.02.014

Cited by 19 publications

(2 citation statements)

References 31 publications

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“…Consequently, it appears necessary to recover the initial dislocation microstructure before the formation of loops. This phenomenon of dislocation network restoration has already been mentioned in the literature in case of stainless steels (Pokor et al ., ; Garner, ; Renault‐Laborne et al ., ). At 300°C, it is not the case because the defects are less mobile and can't move to sinks.…”

Section: Resultsmentioning

confidence: 99%

Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation

Jouanny

Doriot

Malaplate

et al. 2016

Journal of Microscopy

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OATAO is an open access repository that collects the work of Toulouse researchers and makes it freely available over the web where possible. This is an author-deposited version published in : http://oatao. Key words. Charged particle irradiations, dislocation loops, image analysis, irradiation defect evolution, titanium, transmission electron microscopy. SummaryThe complexity and diversity of microstructure involved in titanium alloys make it rather difficult to quantitatively describe defect evolution due to irradiation. This paper focuses on defect evolutions of commercially pure titanium grade 2 under Ti 2+ ion irradiation considering the effect of dose (0.6 and 3 dpa), temperature (300°C and 430°C) and flux (15:1 ratio). An irradiation damage profile was predicted using SRIM software to obtain a homogeneous damage on at least 500 nm depth for TEM observations and simulated using JANNUS-Saclay facility. The details regarding the quantification methodologies of the defects from dark field images are provided, as are the origins of the associated uncertainties. In addition to a tangled dislocation network, presence of the -type and -component loops is observed. The latter was scarcely reported in the literature in the case of titanium alloys. At low temperature, the size distribution of the -type dislocation loops remained similar regardless of the dose and flux whereas these parameters have highly influence at 430°C. A widening of the size distribution and an increase of the threshold incubation dose (TID) was noted with the temperature. In the case of the -component loops, it was shown that the nucleation occurred in spite of the 0.6 dpa low dose.

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Section: Resultsmentioning

confidence: 99%

Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation

Jouanny

Doriot

Malaplate

et al. 2016

Journal of Microscopy

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“…8(a)). Significant differences are mainly reported for higher irradiation temperatures, for several doses and for SA 304L, SA 316 and CW 316 [41].…”

Section: Frank Loop Structurementioning

confidence: 91%

Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 °C

Renault-Laborne

Garnier

Malaplate

et al. 2016

Journal of Nuclear Materials

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Irradiation creep was investigated in different austenitic steels. Pressurized tubes with stresses of 127 e220 MPa were irradiated in BOR-60 at 320 C to 120 dpa. Creep behavior was dependent on both chemical composition and metallurgical state of steels. Different steels irradiated with and without stress were examined by TEM. Without stress, the irradiation produced high densities of dislocation lines and Frank loops and, depending on the type of steels, precipitates. Stress induced an increase of the precipitate mean size and density and, for some grades, an increase of the mean loop size and a decrease of their density. An anisotropy of Frank loop density or size induced by stress was not observed systematically. Dislocation line microstructure seems not to be different between the stressed and unstressed specimens. No cavities were detectable in these specimens. By comparing with the data from this work, the main irradiation creep models are discussed.

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Metal Alloys

PAREIGE,

DOMAIN

2023

Nuclear Materials Under Irradiation

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Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor

Cited by 19 publications

References 31 publications

Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation

Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation

Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 °C

Metal Alloys

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Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor

Cited by 19 publications

References 31 publications

Evolution of defects in titanium grade 2 under Ti2+ ion irradiation

Evolution of defects in titanium grade 2 under Ti2+ ion irradiation

Evolution of microstructure after irradiation creep in several austenitic steels irradiated up to 120 dpa at 320 °C

Metal Alloys

Contact Info

Product

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Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation

Evolution of defects in titanium grade 2 under Ti²⁺ ion irradiation